forschungszentrum karlsruhe in der helmholtz-gemeinschaft association fzk-euratom status of...
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Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
Status of Neutronics Tools & Data for IFMIF-EVEDA
U. Fischer, S. SimakovAssociation FZK-Euratom
Forschungszentrum KarlsruheGermany
Design Review Meeting IFMIF-EVEDA Test Facilities, Forschungszentrum Karlsruhe, March 26-27, 2007
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Dedicated computational tools and data required:
– D-Li neutron source term simulation
– Neutron/photon transport calculations (En> 20 MeV)
– Activation and transmutation calculations (En> 20 MeV)
– Shielding calculations
IFMIF Neutronics
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
D-Li Neutron Source Term
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
• Enhancement to MCNP with ability to sample the generation of d-Li source neutrons on the basis of tabulated double-differential d + 6,7Li cross-sections - Modelling of deuteron beam configuration, orientation and
profile- Use of evaluated d+ 6,7Li data to sample source neutrons- d + 6,7Li cross-sections for deuteron energies up to 50 MeV ( A.
Konobeyev et al, NSE 139 (2001)) - Updated evaluation (new methodology, P. Pereslavtsev, 2005)- McDeLicious standard code for IFMIF neutronics calculations
• Monte Carlo Code McDeLicious Developed to enable a proper representation of the d-Li neutron source term in Monte Carlo transport calculations for IFMIF
D-Li Neutron Source Term
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
0 5 10 15 20 25 30 3510-3
10-2
10-1
100
101
102
Bem, 03 Bem, 03 evaporation prequilibrium stripping 1 level 2 level 3 level 4 level 5 level total
7Li(d,xn), Ed=16.6 MeV
d2 /d/
dE [
mb/
sr M
eV]
Emitted neutron energy [MeV]
New d + 6,7Li Data EvaluationP. Pereslavtsev et al,
2005
0 10 20 30 40 5010-3
10-2
10-1
100
101
102
Baba, 03 evaporation preequilibrium stripping 1 level 2 level 3 level 4 level 5 level total
Li(d,xn), E
d=40 MeV
d2/
d/d
E [
mb/
sr M
eV]
Emitted neutron energy [MeV]
Neutron emission spectra in forward direction
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
McDeLicious validation analyses: Thick Li-target neutron forward yields as function of deuteron incidence energy
0 10 20 30 4010-1
100
101
2001
MCNPX
McDeLicious
Forward Yield ( = 0o)
McDeLi
- Daruga 68 - Weaver 72 - Goland 75 - Amols 76 - Nelson 77 - Lone 77 - Salmarsh 77 - Johnson 79 - Sugimoto 95 - Bem 02 - Baba 01/02
Neu
tron
Yie
ld,
10
10/s
r/C
Deuteron Energy [MeV]
2005
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Neutron Cross-Section Data (E> 20 MeV)
- General Purpose Data Files -
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
• IFMIF project – 1H, 56Fe, 23Na, 39K, 28Si, 12C, 52Cr, 51V, 6,7Li, 9Be (INPE/FZK)- 180,182-184,186W, 181Ta (EFF/JEFF)
• LANL 150 MeV data files (ENDF/B-VI.6)- 1,2H, 12C, 16O, 14N, 27Al, 28,29,30Si, 31P, 40Ca, 50,52,53,54Cr, 54,56,57,58Fe, 58,60,61,62,64Ni, 63,65Cu, 93Nb, 182,183,184,186 W,
196,198, 199, 200, 201, 202, 204 Hg, 206, 20, 208 Pb, 209Bi
• NRG evaluations– 40,42-44,46,48Ca, 45Sc, 46-50Ti, 54,56-,58Fe, 70,72-74,76Ge, 204,206-208Pb, 209Bi
• JENDL-HE data file– 1H, 12,13C, 14N, 16O, 24-26Mg, 27Al, 28-30Si, 39,41K, 40,42- 46,48Ca, 46-50Ti,51V, 50,52-54Cr, 55Mn, 54,56-58Fe, 59Co,
58,60-62,64Ni, 63,65Cu, 64,66-68,70Zn,90- 92,94,96Zr, 93Nb, 180,182-184,186W, 196,198-202,204Hg • Few other evaluations
– KAERI (12C, 27Al, 56Fe, 208Pb), BNL (12C, 56Fe,208Pb, 209Bi), IPPE (232-238U, 237,239Np, 236-244Pu)
Neutron Cross-Sections E 20 MeV - General purpose data ENDF evaluations -
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Iron Transmission Benchmark Experiment (Shin et al.)
0 10 20 30 40 50 6010-14
10-13
10-12
10-11
10-10
Shin et al. 91 MCNP/INPE-FZK MCNP/LANL-150
t = 50 cm
t = 40 cm
Neu
tron
Flu
ence
, n/
cm2 /M
eV/p
roto
n
Neutron Energy, MeV
t = 20 cm
10 20 30 40 501
2
3
4
5
Cierjacks 66 Perey 72 Larson 81 Abfalterer 2001 FZK/INPE LANL-150
To
tal n
eutr
on
cro
ss-s
ecti
on
[b
]
Neutron Energy, MeV
Fe slabs (20, 40 50 cm) irradiated with source neutrons produced by 65 MeV protons on Cu target
Fe(nat) total neutron cross-section
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Activation and Transmutation - Tools & Data -
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
• Intermediate Energy Activation File IEAF-2001 (FZK/INPE)– Complete cross-section data library for activation and transmutation analyses up to En 150 MeV (1 Z
84)– Uses lumped MT=5 reaction cross-sections with production yield vectors (LAW=0) on MF=6 file– Validated through series of benchmark calculations, tested and qualified for SS-316 & V/V-alloy samples in
IFMIF activation experiments
Can be used with ALARA activation code (P. Wilson, UW) – Analytical and Laplacian Adaptive Radioactivity Analysis– Capable of handling an arbitrary number of reaction channels
Activation and Transmutation- Tools and Data -
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
• European Activation File EAF-2005 (UKAEA)– EAF data library extended to 60 MeV (based on TALYS + SAFEPAQ)– EAF data format using non-standard MT-numbers– Can be used with FISPACT-2005 inventory code (EASY system, UKAEA)– 62,637 reactions from 50 data sources, 86 different reaction types– Extended decay data library with 2,192 nuclides
• EAF-2007: deuteron induced reactions– 66,864 reactions from different sources, mostly TALYS (– New calculated data library produced by TALYS for data using global
parameters, included long-lived isomers as targets– New calculations using TALYS with local parameters produced by M.
Avrigeanu for 27Al, 54,56,57,58Fe and 63,65Cu (<50 MeV)
• EAF-2007: proton induced reactions– 67,925 reactions, only based on data from TALYS calculations (so far)
FISPACT-2007 modified to handle d and p as incoming particle
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
NPI Rez Activation Experiments
MCNPX model
D2O Target (Ø30×26 mm2)
Activation Foils
1.7 mm 47 mm ≈ 700 cm
NeutronDetector
24
6
10
12
0 5 10 15 20 25-5-4-3-2-1012345
Ep = 36.5 MeV, p-Flux [1/cm2]
D2O -depth/p-beam direction, mm
Hor
izon
tal d
irec
ton,
mm
37 MeV protons
1 10 4010-2
10-1
100
Spectrum used Activation Caclution
D2O(p,xn), E
p = 37 MeV
Rez Experiment
Neutron Energy, MeV
MCNPX/LA-150
= 0o
Spe
ctra
l Yie
ld,
1010
n/s
r/M
eV/
C
Hf-
179n
Hf-
180m
Hf-
181
Hf-
182m
Hf-
183
Ta-
182
Ta-
183
Ta-
184
Ta-
185
W-1
81
W-1
85
W-1
87
10-1
100
101
102
103
EAF-2005
IEAF-2001
C/E
W Activation ProductsC/E ratios of –radio-activities induced in W
p-D2O neutron spectrum
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Neutron Spectrum Unfolding Technique
- 37 MeV @ 12 μA proton beam- Heavy water target- Dosimetry foils:
Al, Ti, Fe, Co, Ni, Y, Nb, Lu, Au (Ø12 x 0.1-0.3 mm)
- 10-12 hours irradiation- γ-activities measured by HPGe
detector at cooling 1 h to 100 day;- Guess spectrum: measured by
NE213 detector and simulated by MCNPX.
0 5 10 15 20 25 30
0.5
1.0
1.5
2.0
2.5
24Na196Au
196m2Au
195Au
194Au
198Au 92mNb
90mY
88Y
90mY
57Co
58Co59Fe56M
n
60Co
46Sc48Sc
47Ca57Ni57Co
58Co 60Co
Lu173
Lu174
Lu174m
Lu176m
56Mn
54Mn
51Cr
169 Tm,209Bi(n,3-6n)
115 In,93Nb,103 Rh(n,n')
108
109
1010
2x1010
5th-iteration (final)
Act
ivit
y(C
al)/
Act
ivit
y(E
xp)
Neutron Energy, MeV
D2O(p,xn), E
p = 37 MeV @ 12 A
Guess (initial)
Spe
ctra
l Flu
x, n
/cm
2 /s/M
eV
• Use of modified SAND-II code with cross sections from EAF-2005
• Tested at the NPI cyclotron in neutron spectrum extending up to 35 MeV.
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
0 20 40 60 80 100 120 1400
200
400
600
800
1000
1200
Fe(n,xp)
LANSCE, 05 EAF-2005 IEAF-2001 GNASH JEFF-3.1
C
ross
sec
tion
[mb]
Neutron energy [MeV]
0 20 40 60 80 100 120 1400
20
40
60
80
100
120
140
160
180
200
Fe(n,x)
LANSCE, 05 EAF-2005 IEAF-2001 GNASH JEFF-3.1
Cro
ss s
ect
ion
[m
b]
Neutron energy [MeV]
0 20 40 60 80 100 120 1400
20
40
60
80
100
120
181Ta(n,x)
LANSCE, 05 EAF-2005 IEAF-2001 Konobeyev GNASH
Cro
ss s
ect
ion
[m
b]
Neutron energy [MeV]
0 20 40 60 80 100 120 1400
200
400
600
800
1000
1200
Ta(n,xp)
LANSCE, 05 EAF-2005 IEAF-2001 GNASH
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
Gas production cross-sections
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Radiation Shielding
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
• Dedicated approach for coupled 3D Monte Carlo and deterministic (SN) transport calculations for IFMIF shielding analyses
• Monte Carlo technique used to simulate the particle generation and transport in and around the neutron source region
• Discrete ordinates (SN) method used to treat the deep penetration problem in bulk shield.
• Mapping approach for calculating SN angular fluxes from scored data of Monte Carlo particle tracks crossing a specified surface
• Implemented in interface programme linking MCNP/McDeLicious and 3D SN code TORT of DOORS3.2 package
Radiation Shielding
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
3-D shielding calculations for IFMIF Test Cell
Dose rate distribution in access room
Geometry model
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
McCad Model Generation
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
CAD Interface Programme McCAD
• Automatic conversion of CAD geometry data into semi-algebraic geometry representation for the MCNP Monte Carlo code
- CAD data are imported via data files in neutral format (IGES, STEP)
- Graphical User Interface (GUI) with components for modelling, visualization, and data exchange
- McCAD is able to perform the conversion of the CAD data into MCNP geometry including the generation of voids and error analyses and repair (generation of full MCNP input deck)
- McCAD can also generate CAD geometry models from available input decks (e. g. for visualization)
- Successful test applications to JET and ITER (benchmarking)
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Test Cell Model Converted by McCAD
2D cuts generated by MCNP geometry plotter
Vertical cut of test cell Horizontal cut at target mid-plane level
Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft
Association FZK-Euratom
U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007
Summary• Codes for IFMIF neutronics
– Transport: McDeLicious, MC/TORT, (MCNPX) – Geometry preparation: CAD/McCAD– Activation/transmutation: ALARA, FISPACT Need to be further developed, in particular: McDeLicious,
MC/TORT, McCAD
• Nuclear Data for IFMIF neutronics– Transport calculations: different sources, urgent need for qualified
IFMIF reference data library (IAEA) – Activation/transmutation: IEAF-2001, EAF-2005/07 (n, p, d), to be
further developed, improved and validated– Validation experiments, to be extended/continued– To be newly developed: dosimetry data file (extended IRDF)