1. description/status of sesameat sesame the alara principle is applied by guaranteeing the...
TRANSCRIPT
7th International Workshop on Radiation Safety May8‐102013BNL
CONTENTS1 Description Status of SESAME 2 Shielding objectives beam losses assumptions3 Analytical Swanson Jenkins and FLUKA (latest)4 Radiation estimations5 Gas bremsstrahlung estimations for the straight section6 Storage ring recommendations7 SESAME general strategy 8 Mazes and ducts 9 Skyshine10 XRFXAFS beamline
1277th International Workshop on Radiation Safety May8‐102013BNL
1 DescriptionStatus of SESAME
1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)
3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)
2277th International Workshop on Radiation Safety May8‐102013BNL
Natural emittances εx εz 256400 02564 nmrad
Decay mode Beam life time ~ 20hrs
3rd generation light source
IR
XAFSXRF
VBL
3277th International Workshop on Radiation Safety May8‐102013BNL
Booster
SR
SR
EH
21 Shielding objectives
The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation
The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear
Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear
Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear
Total number of electrons injected per year 15 1015 electronsyear
4277th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
CONTENTS1 Description Status of SESAME 2 Shielding objectives beam losses assumptions3 Analytical Swanson Jenkins and FLUKA (latest)4 Radiation estimations5 Gas bremsstrahlung estimations for the straight section6 Storage ring recommendations7 SESAME general strategy 8 Mazes and ducts 9 Skyshine10 XRFXAFS beamline
1277th International Workshop on Radiation Safety May8‐102013BNL
1 DescriptionStatus of SESAME
1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)
3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)
2277th International Workshop on Radiation Safety May8‐102013BNL
Natural emittances εx εz 256400 02564 nmrad
Decay mode Beam life time ~ 20hrs
3rd generation light source
IR
XAFSXRF
VBL
3277th International Workshop on Radiation Safety May8‐102013BNL
Booster
SR
SR
EH
21 Shielding objectives
The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation
The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear
Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear
Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear
Total number of electrons injected per year 15 1015 electronsyear
4277th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
1 DescriptionStatus of SESAME
1‐ A 225MeV circular microtron hasbeen commissioned first beam was onMonday 28 November 2011 at113am2‐ The transport line from microtron tobooster (TL1)
3‐ A 800 MeV booster synchrotronsuppose t be commissioned by the endof 20134‐ The transport line from booster to storage ring (TL2)5‐ A 25GeV 400mA storage ring firstday beamlines suppose t becommissioned by the beginning of2016 (hopefully)
2277th International Workshop on Radiation Safety May8‐102013BNL
Natural emittances εx εz 256400 02564 nmrad
Decay mode Beam life time ~ 20hrs
3rd generation light source
IR
XAFSXRF
VBL
3277th International Workshop on Radiation Safety May8‐102013BNL
Booster
SR
SR
EH
21 Shielding objectives
The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation
The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear
Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear
Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear
Total number of electrons injected per year 15 1015 electronsyear
4277th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
3277th International Workshop on Radiation Safety May8‐102013BNL
Booster
SR
SR
EH
21 Shielding objectives
The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation
The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear
Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear
Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear
Total number of electrons injected per year 15 1015 electronsyear
4277th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
21 Shielding objectives
The basic principle of radiation protection is the ALARA (As Low As ReasonablyAchievable) principle which states that exposure to any person should be kept as lowas reasonably achievable At SESAME the ALARA principle is applied by guaranteeingthe radiation limits for non‐exposed workers (1mSvy corresponding to 05mSvh for2000 working hours per year) except in controlled areas where access will not bepossible during operation
The number of electrons per year stored in the storage ring is estimated as (a 400mAstored beam current in the 1322 m long storage ring corresponds to 11 1012electrons stored)Normal operation3 injections per day 250 days operation per year 862 1014 electronsyear
Unwanted beam tripsMean time between failure = 24 hours 275 1014 electronsyear
Accelerator RampD program1 day per week 10 injections per day 393 1014 electronsyear
Total number of electrons injected per year 15 1015 electronsyear
4277th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
The following beam loss distributions have been assumed for the shieldingcalculations of the storage ring
‐ 80 (303mW) of the total losses in any single point in the injection area‐ 10 (379mW) of the total losses in any single point in any other point alongthe storage ring
We use this local loss distribution pattern to calculate both average dose ratesover one year (total loss power 379mW) and to calculate the integrated dosein case of a total beam loss (total energy 441 J)
527
22 Beam loss assumptions
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
31 Analytical formula
The standard analytical shield model has been used for the SESAME shieldingcalculations This standard model gives an expression for the effective dose rate in apoint behind a shield wall due to a local beam loss of a given power
r
i
d
r
R
ePCE
ri
i
2
With Effective dose rate in Svh-1
Cr the conversion factor for the rth type of radiation in Svh-1kW-1m2
P the electron loss power in kWR the distance between the loss point and the point of observation in mdi the effective thickness of the ith wall in cmλir the attenuation length of the material of the ith wall for the radiation of type r in cm
The following conversion factors are used (Svh-1kW-1m2) Gamma dose rate at 0 degrees Cg0 = 300 times E0 with E0 the electron energy in MeVGamma dose rate at 90 degrees Cg90 = 50Giant resonance neutrons CGRN = 10High energy neutrons CHEN = 155
Shielding material Density(gcm3)
Attenuation length (cm) for Gamma
Attenuation length (cm) for (GRN)
Attenuation length(cm) for (HEN)
Ordinary Concrete 230 213 174 2766
Pb 1135 22 142 168
Steel 787 43 127 175
Table31 Attenuation lengths and densities for different shielding materials
6277th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
32 Swanson
Swanson gives leakage dose rates of gamma (Eege1GeV) and neutrons (Eege50MeV) in forward direction as follows
r
i
d
e
R
ePEE
ri
i
2
6 10
r
i
d
HENR
ePE
ri
i
2
4
r
i
d
GRNR
ePE
ri
i
2
722
Where
Effective dose rate in Svh-1
P the electron loss power in kWdi the effective thickness of the ith wall in cmR the distance between the loss point and the point of observation in mλir the attenuation length of the material of the ith wall for the radiation of type r in cm Attenuation coefficients are summarized in table (32)
Shield material Attenuation length (cm)λϒ λHEN λGRN
Lead 21 667 238Ordinary Concrete (23gcm3) 182 400 169Iron 45 588 185
Table32 Attenuation length for different shielding materials in forward direction
7277th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
33 JenkinsJenkins formula gives lateral dose rates for both gamma and neutron at Eege150MeV and le 20GeV and angle θge300 and le1300
2
21
214
cos7201
)cosexp(26701cos9801
)cosexp(133
11063
iri
iri
e df
ecd
REJE
iGRN
iIEN
iHEN
en
ecdZ
df
ecdf
REJE
)cosexp(793cos7501
)cosexp(10cos7201
)cosexp(
11063
730
2
2
1
214
Whereeffective dose rate Ee electron energy in GeV
Z atomic number of the shielding materialλGRN λIEN and λHEN Attenuation lengths for giant resonance intermediate energy and high energy neutrons respectively for different shielding materials see table (33)J number of electron loss in secondθ and φ are the inclined degrees from the electron beam axis to a measurement point and the shield material respectivelyƒ1 ƒ1 corrections factors of a source reduction for high and intermediate energies ( lt5GeV)
Shieldingmaterial
Density gcm3 Attenuation Length (cm)λϒ λGRN λIEN λHEN
Lead 113 21 100 183 227Iron 78 43 68 124 213OC 23 181 131 239 522
Table33Attenuation length for different shielding materials in lateral direction
827
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Table 41a Total dose rate and accumulated dose in the forward direction at different locations
41 Radiation estimations (NOT Gas Brem) In the direction of experimental hall (forward direction)
Radiation loss sourceIn the direction of experimental hall
Total dose rate in (microSvh) - accumulated dose in (microSv) in forward directions usingAnalytical Swanson FLUKA
SSS- Normal loss (10) 20208 3023 003SSS-Single loss 651186 9495 091LSS- Normal loss 28844 4314 002LSS- Single loss 92950 13913 09LSS-Injection area Normal loss 15195 1509 004LSS-Injection area Single loss 61209 6087 12
Table41b Total effective dose rate and accumulated dose in the forward directionstowards the experimental hall at different locations with using 15 cm thickness of lead
Radiation loss sourceTotal dose rate in (microSvh) - accumulated dose in (microSv) in forward directions with
15 cm in thickness leadAnalytical Swanson
SSS- Normal loss in microSvh 023 025 SSS-Single loss in microSv 728 8LSS- Normal loss in microSvh 032 035 LSS- Single loss in microSv 104 11LSS-Injection area Normal loss in microSvh (80) 017 014LSS-Injection area Single loss in microSv 067 7
927
Fig41 SR straight sections
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Normal operation losses and the direction losses in microSvh
Total dose rates - accumulated dose perpendicular to losses directions
Analytical Jenkins FLUKA Normal loss (exp hall) 044 042 004Injection area normal loss (exp hall) 024 065 0004Normal loss (service area) 077 14 0045Injection area normal loss (service area) 072 19 001Normal loss (roof) 044 094 003Injection area normal loss (roof) 024 093 006
Table42 Total dose rate and accumulated dose in the perpendicular directions
42 Radiation estimations (NOT GB) in all directions of the injection area
1027
Fig42 Booster to SR Injection part
7th International Workshop on Radiation Safety May8‐102013BNL
Service area
Experimental area
TL2
Fig41 SR straight sections
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
5 Gas bremsstrahlung estimations from the straight sections
Energy 2500 MeVCurrent 400mA 25E18esLong straight section (LSS) 71m
Short straight section (SSS) 505m
ID vacuum chamber pressure 2e-7 Pa 20e-9 millibar
Distance to Safety shutter 925m for SSS735 m for LSS
Real distance to ratchet wall 1035m for SSS85m for LSS
Table51a SESAME front ends parameters
1127
Fig51a Not used beamlines lateral view
7th International Workshop on Radiation Safety May8‐102013BNL
dLSSPe‐beam W
Fig51b used beamlines lateral view
LSSPe‐beam Pb
Not to Scale
Ray tracing
Lead collimators
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
atmppILE
43216-
0 10 17 10mD
by Rindi and Tromba
0
672
227-
0 10 25 (Svh)DppI
dLdL
mcE
Ferrari
by Frank
0
2
26-
0 10 3 (Svh)DXI
dLdL
mcE
Where X0 = radiation length of air at 10‐9 Torr equal to 234e16 cm L = effective length of the straight path I = beam current in es and E = electron beam energy in MeV d= distance to upstream face of the safety shutter
12277th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Empirical formula used Gas bremsstrahlung Dose Rate(Svh)LSS
Gas bremsstrahlung Dose Rate(Svh)SSS
Rindi and Tromba 1074 0764
Ferrari 45 25
Frank 16 09
Table51b Total dose rates just before Safety shutter
t- exp D D 0A
Used formulaDose rates
After 20 cm safety shutter LSS in microSvh
Dose ratesAfter 20cm safety shutter
SSS in microSvhRindi and Tromba 025 0177
Ferrari 104 058Frank 037 021
Table51c shows the difference in the estimated values using three different empirical formulas
WhereD0 is the dose rate just before the shatter in SvhDA is the dose rate just after the shatter in microSvhρ tungsten density ~ 19 gcm3 (depends on used W alloy)micro Minimum photons attenuation coefficient 00402cm2gt Tungsten thickness in cm
13277th International Workshop on Radiation Safety May8‐102013BNL
WD0 DA
t
Fig51c MSS
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
1- 1m OC plus 15 cm of lead in thickness on the ratchet end walls will fulfil our needs2- 1m OC for the Ratchet side wall with increasing the wall thickness in the injectionarea (13 and 135 m) towards experimental hall and 08 m thickness of ordinaryconcrete for inner storage ring shielding wall is enough and 125m in the injection area3- 1m OC (double overlapped layers) for the ring roof tunnel except 15m (tripleoverlapped layers) for the injection area4- 20cm tungsten alloy (19gcc) safety shutter (only one safety shutter) GB raytracing collimation needed5- PE if needed to be added
6 Storage Ring Tunnel Recommendations
14277th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Finally SESAME general strategy during commissioning or normal work1- Start with mentioned (Initial) thicknesses for both concrete and the lead2- Monitor measuring instantaneous effective dose rates passive area monitors will also be used to integrate doses in various areas and evaluate during commissioning via complete controlled system particularly for the microtron3- Extra thicknesses will be added if needed to get non radiation areas (le 05microSvh coming only from radiation losses however keeping in mind there is any way the background which is not included in our estimations) looks like
a- Service areab- Storage Ring Roof c- Booster Roof d- Experimental Halle- Inside the inner booster shielding wall
4- Keeping some areas as controlledsupervised areas (gt 05microSvh)
7 SESAME general strategy
15277th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
81Radiationstreaming fromSESAMEstorageringmazes
Storage ring tunnel has two mazes each contains four clear legs with cross sections (12mtimes27m) the legs length in a series order is 34m 2m 2m and 3m The calculations were taken in both single loss and normal losses scenariosEmpirical formula KTesch and FLUKA were taken in our calculations and all the expected values were within the predefined value which is 05 microSh for normal losses and even for single beam lost the expected reading is very low value
For the first leg gamma ray dose attenuation ratio γ1 is3
11 )L(d 022 And
3)L(d 026 ii (i=2 3hellip) for other legs
While for neutrons 8181 02201)352exp(0220)450Lexp( 2 iiiii ALAN
Where i=1 2hellip AndLi the length of the ith leg in md the half width of the maze leg in mAi the cross section of maze leg in m2 For the last leg the factor 2 in formula is removed
The leakage dose outside the maze can be calculated using an empirical formula given by KTesch
16277th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Losses scenario Exist (door) Formula FLUKANormal losses in microSh 00026 00274
Single losses in microS 0088 075
Table81 Total gamma and neutron dose rates and accumulated doses at exit doors
Fig81 shows FLUKA simulation for SR maze for Normal and one single loss accident
17277th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
82 Cabling and cooling ducts radiation streaming
2
22N1N41F F)(D Svh)(D 0
LdhSv NN
2
221 41F F)(D Svh)(D 0
LdhSv
Simon‐Clifford formulaWhereD N
0 D ϒ0 Neutron and gamma dose rates at duct entrance center surface
respectivelyDN Dϒ Neutron and gamma dose rate at duct exit center surface respectivelyd duct diameter in cmL duct length (depth) across shielding in cm
21221 )(cos F zxxrx
1
2 )cos(2
1 F
d1
2 )cos(2
1 F
NN
d
e‐beam
floor
Lat Sh wall
Cabling amp cooling
θ
1827
Fig82a Real duct
Fig82b Cross section duct center
x
zr
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
microN microϒ = linear attenuation coefficient 137cm and 189 cm for neutron and gamma respectivelyαN αϒ Albedo coefficients (01) for neutron and (10) for gamma respectively
Duct dimensions
WtimesHtimesL
Total dose rate normal
operation inside duct
surface center microSvh
Total doseSingle loss inside duct surface center
microSv
Total dose rate normal loss operation
outside duct surface center
microSvh
Total doseSingle loss
outside duct surface center
microSv
Anal FLUKA Anal FLUKA Si-Cl FLUKA Si-Cl FLUKA
10020 80 5312 865 171167 28284 286 053 9223 1754602080 5312 804 171167 26187 1917 05 61727 160802080 5312 75 171167 244 2399 061 77241 1954502080 5312 803 171167 25756 1668 036 537 119202080 5312 803 171167 25908 0854 0222 275 418
1015120 a 4243 6485 171167 2652 1567 001 631 01 R=5cmb 7471 120 240735 4083 0193 04 62 87R=5cmc 9030 1754 290996 5712 0233 0016 75 0386
a injection areab Visible beam line opening centered at 30 cm above floor 10cm diameterc IR beamline opening centered at 70 cm above electron beam height 10 cm diameter
Table82 Dose rates at duct entrance and exit for some cabling and cooling ducts
19277th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
9 Estimates of Skyshine
Rindi and Thomas
20
0 Svh)(D rerDa
Where a = 7 (constant) D0 = unshielded dose rate on the concrete roof (source term) r = distance of the dose point from the source in meters and λ = 3300 meters effective air attenuation factorFor conservative case 15E+15 ey (~1370 injectionsy including normal operation accidental beam losses and machine day losses) will be extracted to the storage ring and were lost at full 25GeVTable 91 gives the calculated skyshine estimates at 50 and 100 meters from common single storage ring lost point over one full year of operation and we can see all values are under tolerable absorbed dose level for public
Neutron sourcecomponent
Dose rate on theconcrete roof
mSvy
Skyshine Doseat 50 mmSvy
Skyshine Doseat 100 mmSvy
Giant resonance neutrons 2518 000694 000171High-energy neutrons 2555 000704 000173
Total skyshine dose 5073 001398 000344
Table91 Skyshine dose along 1 year at 50m and 100m from SESAME roof
20277th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
10 Preliminary shielding design for first day SESAME XAFSXRF BMBeamline against to Synchrotron Radiation source and electron losses
Table101 Beam parameters Electron energy 25GeVElectron Current 04 ACircumference 1332 mNumber of bending magnets 16Bending Dipole field 145545 TMagnetic radius 573 mDipole port 65 degreesCritical energy 605KeVPhoton energy range 5‐30KeVSR total power in 2π 2415KWFan width 384KWmradHorz opening plusmn3mradVertical opening plusmn196mrad
Fig101 Hutches layout
Photon beam
OHEH
Ratchet wall
Control room
21277th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
ComponentsPosition (m)With respect
To Notes
Source RWFilter 865 3 C filters with different thicknesses 50 microm 200 microm and 1 mm
Be window 1134 0557 A and water cooled 250 microm thickness be window
Mirror (VCM) 126 1817 -Upwards reflecting mirror -collimating the beam for a better energy resolution-Double stripes Si and Pt coating-Dimensions120x7 cm2
Be window 140 3217 Still under discussion (can be replaced just by a vacuum valve)
Double Crystal Monochromator(DCM)
151 431 -The axe of rotation is the center of the first crystal- 1st crystal water cooled -Dimensions10x4 cm -Sagital focusing 2nd crystal- Gap between the 1st and 2nd crystal is 18 mm
Mirror 1825 745 -Vertically focusing (11 demagnification)-Double stripes Si and Pt coating-Dimensions120x7 cm2
Exit window 275 1670 Be window with a thickness of 250 microm
Sample position (S1) 3075 -Six degrees of freedom sample manipulator will be placed - considered as a geometric source for the focusing KB system
VFM mirror (KB) 3325 2245 -Dimensions (20x25 cm)-Rh coating-Reflect upwards-Focus the beam in vertical
HFM mirror (KB) 3355 2275 -Dimensions (20x25 cm)-Rh coating-Reflect horizontally-Focus the beam in horizontal
Sample position (S2) 3370 -Beam size at the focal point (~10x10 microm)
Table102 XRFXAFS optical components roles and their position in the beamline with respect to the source point and downstream ratchet wall
2227
Some main components came from different light sources as a donationsIn addition of designing and manufacturing a new components
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
‐1E+09
0
1E+09
2E+09
3E+09
4E+09
5E+09
6E+09
7E+09
8E+09
0 5 10 15 20 25 30
pseVmradmA
Photon energyKeV
Fig102 Photon Spectrum through C filter
0E+00
1E+10
2E+10
3E+10
4E+10
5E+10
6E+10
1 11 21 31 41
peVsecmradmA
Photon energyKeV
Fig103 Spectrum of photon source
23277th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Results of STAC‐8 simulations for Optical Hutch
Table 103 Effective dose rates (only for SR) rates outside lateral right optical hutch shielding wall
Right lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 2602 1153 1054 015
Table 104 Effective dose rates (only for SR) outside optical hutch roof
Roof wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 382 1653 016
Table 105 Effective dose rates (only for SR) outside lateral left optical hutch shielding wall
Left lateral wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 112 053 005
Table 106 Effective dose rates (only for SR) outside back wall optical hutch shielding wall
Downstream wall hutch thickness in addition to 2mm Fe Pb (mm)
Effective dose rate inmicroSh
1 3653 225 4 0325
Additional lead around the photon beam tube downstream hutch wall
24277th International Workshop on Radiation Safety May8‐102013BNL
Lead hutches donation
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
92 Transport beam pipe
93 Experimental Hutch (less than 03microSh)bullDownstream wall 2mm steel thickness with 1mm leadbullLeft wall 2mm steel thicknessbullUpstream wall 2mm steel thicknessbullRoof 2mm steel thickness
Dose rate outside 1mm Fe covered with 1mm Lead for 5cm tube diameter is less than 03 microSh
25277th International Workshop on Radiation Safety May8‐102013BNL
94 OH basic FLUKA simulation
Fig94a OH Lateral viewFig94b OH top view
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Very basic FLUKA simulations (Not including gas bremsstrahlung) for optical Hutch were taken place (STAC-8 thickness values) showing TDR less than 1microSh ( for normal losses and less than 30microS TD for single loss outside hutch back wall
2627
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
Special thanks
Dr Y Asano
7th International Workshop on Radiation Safety May8‐102013BNL2727
7th International Workshop on Radiation Safety May8‐102013BNL
7th International Workshop on Radiation Safety May8‐102013BNL