efit-pb transient analysis m. schikorr, e. bubelis eurotrans: dm1 wp1.5 : “safety”
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Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 1
EFIT-Pb Transient AnalysisEFIT-Pb Transient Analysis
M. Schikorr, E. BubelisM. Schikorr, E. Bubelis
EUROTRANS: DM1 WP1.5 : “Safety”
Karlsruhe , 27-28 November 2008
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 2
1. Reactivity Coefficients for EFIT-Pb
2. SIM-ADS Transient Results for EFIT-Pb
3. Status D1.43 Deliverable : Transient Analysis of EFIT-Pb
Topics:
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 3
EFIT-Pb Reactivity Coefficient Calculations:Basic Data Source : G.Glinatsis, „EFIT-MgO/Pb Core Design Reactivity Coefficients” Genova, April Meeting 2008, and D-1.36
3.) Coolant density Effect: 1% dens
whole Active Core zones: (DK/K )/ 1% dens = 0.00058 0.00002
2.) Fuel Temperature Effect:
BoL: Keff = 0.96123 0.00027 (0.96147 0.00025);
BoC: Keff = 0.96183 0.00025 (0.96207 0.00025)
EoC: Keff = 0.96227 0.00026; (0.96227 0.00026).
4.) (ΔKeff/Keff) due to all „Thermal Expansions“:
from 400°C to HFP = − 0.00549 ± 0.00034.
T nom_fuel =1800 K
HFP Conditions:
T_fuel = 910 °C,
T_cool = 440 °C
1.) 400 °C Isothermal Conditions: K_eff_ref = 0.96654 +/- 0.00019
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 4
Calculated k_eff for different EFIT-Pb core states using MCNPX :
Basic Data Source : D1.36 (Glinatsis data)
Ref_state Isothermal
HFP T_fuel=1527°CCore region
Voided
T_cool_in [°C] 400 400 400 400
T_cool [°C] 400 440 440 voided
T_fuel [°C] 400 910 1527 910
BOL 0.96654 0.96123 0.96147 1.02740
BOC 0.96183 0.96207 1.02595
EOC 0.96227 0.96227 1.02373
K_eff for EFIT-Pb as calculated by MCNPX
Note : For the Safety Calculations the value of k_eff = 0.97403 at HFP and BOC is adopted. Value taken from Table 5.3, Ref [D-1.36]
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 5
Reactivities changes [pcm] for different EFIT-Pb core states using previous k_eff data from Glinatsis:
from 400°C (Ref_state) to
HFP
from HFP to T_fuel = 1527 °C
state
from HFP to Voided state
Axial Expansion Effect
[pcm] [pcm][pcm /1%density
change][pcm]
BOL -571.5 26.0 -67.0 -636.7
BOC -506.6 25.9 -64.7 -570.5
EOC -459.1 0.0 -62.4 -487.3
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 6
Calculated EFIT-Pb Reactivity Temperature Coefficients using prevoius Glinatsis k_eff data :
Fuel Temperature
Coeff: A_dopp [pcm]
Coolant Temperature
Coeff: [pcm/°C]
Axial Fuel Thermal
Expansion Coeff: [pcm/°C]
Diagrid expansion Coeff:
[pcm/°C] *
BOL 61.9 0.76 -1.25 -1.50
BOC 61.4 0.73 -1.12 -1.50
EOC 0.0 0.71 -0.96 -1.50
* assumed
2.) To calculate Coolant temperature reactivity coefficient need Pb coolant density.
Used : density lead = 11042 – 1.194*T_cool [°C] [kg/m^3]
1.) Diagrid expansion coefficient could not be extracted from the Glinatsis data as coolant inlet temperature remained at 400 °C for all different k_eff calculations. Thus assumed radial expansion coefficient = - 1.5 [pcm/°C], similiar to what is being observed in SPX1.
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 7
T_coolin T_cool T_fuel°C 400 440 910
HFP: BOL BOC EOCCoolant (pcm) 0.0 0.0 0.0Fuel Doppler (pcm) 0.0 0.0 0.0Fuel Expansion (pcm) 0.0 0.0 0.0Grid_Expansion 0.0 0.0 0.0Total [pcm] 0.0 0.0 0.0k_eff HFP 0.96123 0.97403 0.96227k_eff @ Temp_Iso 0.96123 0.97403 0.96227Margin to Criticality [$] -18.02 -24.1beta [pcm] 148 163Margin to Criticality [pcm] -2666 -3921
T_coolin T_cool T_fuel°C 380 380 380
HFP to CZP : BOL BOC EOCCoolant (pcm) -45.4 -43.9 -42.3Fuel Doppler (pcm) -36.8 -36.5 0.0Fuel Expansion (pcm) 661.7 592.9 506.4Grid_Expansion 30.0 30.0 30.0Total [pcm] 609.5 542.5 494.1k_eff HFP 0.96123 0.97403 0.96227k_eff @ Temp_Iso 0.96689 0.97920 0.96687Margin to Criticality [$] -14.35 -21.0beta [pcm] 148 163Margin to Criticality [pcm] -2124 -3427
T_coolin T_cool T_fuel°C 30 30 30
HFP to Ambient: BOL BOC EOCCoolant (pcm) -310.5 -299.9 -289.1Fuel Doppler (pcm) -84.3 -83.7 0.0Fuel Expansion (pcm) 1098.7 984.5 840.8Grid_Expansion 555.0 555.0 555.0Total [pcm] 1258.9 1155.9 1106.7k_eff HFP 0.96123 0.97403 0.96227k_eff @ Temp_Iso 0.97300 0.98512 0.97263Margin to Criticality [$] -10.20 -17.3beta [pcm] 148 163Margin to Criticality [pcm] -1510 -2814
Reactivity Balance going
1.) from HFP to CZP (T=380°C), and
2.) from HFP to Ambient (T= 30°C)
for EFIT-Pb for various Core states (BOL, BOC; EOC) using the various EFIT-Pb reactivity coefficients from previous slide
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 8
1. EFIT Pressure Drops: as proposed by Ansaldo after SA redesign leading to lower SA inlet and outlet pressure drops.
Ansaldo calculated pressure drops [14], mbar
Corresponding pressure drop coefficients (based on
coolant flowrate of 185 kg/s per SA)
SA Inlet 289 5.50 SA Outlet 86 1.64 Flow along smooth pin section
165
Grid spacers (6) * 94.4 Total core pressure drop 634.4 Total core pressure drop taking into account ~10 % uncertainty
700
Main HX (SG) [15] 400 7.61 Main pump [15] 270 5.16 Total pressure drop of the whole primary system
1370
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.Schikorr EUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008
9
The EFIT Reactor Design:
4
EFIT is a pool-type reactor of about 400 MW power
Sub-critical reactor (Keff = 0.97) sustained by a spallation neutron source (beam proton energy 800 MeV and beam current 20 mA)
Reactor core with 3 U-free fuel zone with (Pu,MA)O2 in MgO matrix to improve the burning efficiency
Pure melt lead as primary coolant (lower cost and less activation products such as Polonium than LBE)
Core power is removed by forced circulation (4 pumps placed in the hot collector) through 8 steam generators with helical-coil tube bundle
4 DHR heat exchangers are immersed in the annular cold pool between the inner vessel and the reactor vessel
DHR
Steam generator
DHR
Steam generator
Pump
Core
Target
Reactor vessel
Inner vessel
heat exchanger
EFIT Reactor Block
Proton Beam
Figure Source: G. Bandini, P. Meloni, M. Polidori (ENEA - Bologna)
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 10
SIMMER-III ANSALDOResults at after 1 hourt = 3600 s: (P = 16 MW)
mC = 2740 kg/s
mD = 2983 kg/s 2985 Kg/s
TCi = 410.5 C
TCo = 449.1 C
TDi = 444.6 C 444 C
TDo = 407.0 C 407 C
y = mC(TDi - TDo)
(TCi - TDo)
x = y + mD - mC
y = 255 kg/s
Recirculation ratio at DHR outlet:x = 498 kg/s (17% of mD)
Simplified scheme of RELAP5 model
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
SIMMER-III ANSALDOResults at after 1 hourt = 3600 s: (P = 16 MW)
mC = 2740 kg/s
mD = 2983 kg/s 2985 Kg/s
TCi = 410.5 C
TCo = 449.1 C
TDi = 444.6 C 444 C
TDo = 407.0 C 407 C
y = mC(TDi - TDo)
(TCi - TDo)
x = y + mD - mC
y = 255 kg/s
Recirculation ratio at DHR outlet:x = 498 kg/s (17% of mD)
Simplified scheme of RELAP5 model
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
Figure Source: G. Bandini, P. Meloni, M. Polidori (ENEA - Bologna)
The In-vessel Flow Paths during normal Heat Removal mode:
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.Schikorr EUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008
11
The Decay Heat Removal (DHR) System of EFIT-Pb
The DHR system is conceived for inherently safe decay heat removal and passive mode actuation
4 independent loops partially filled with organic oil, that dissipate the decay heat to the atmosphere by natural convection circulation
Each loop consists of a dip cooler immersed in the cold pool where the oil partially vaporize and an air-vapor condenser with stack chimney and interconnecting piping
Oil boiling point is determined by superimposed pressure of an inert gas
In normal operation the oil is below its boiling point and the DHR removes only heat losses from SGs and inner vessel (few 100 kW) to keep cold the upper part of the reactor vessel
Condensed Oil
Boiling Oil
Cooling air Chimney
Air Vapour Condenser
Nitrogen Header
Oil VapourSeparator
Condensed Oil Drum
EFIT ReactorSafety-Related DHR Loop
DHRDip Cooler
Inner vessel
Reactor vessel
Figure Source: G. Bandini, P. Meloni, M. Polidori (ENEA - Bologna)
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 12
SIMMER-III ANSALDOResults at after 1 hourt = 3600 s: (P = 16 MW)
mC = 2740 kg/s
mD = 2983 kg/s 2985 Kg/s
TCi = 410.5 C
TCo = 449.1 C
TDi = 444.6 C 444 C
TDo = 407.0 C 407 C
y = mC(TDi - TDo)
(TCi - TDo)
x = y + mD - mC
y = 255 kg/s
Recirculation ratio at DHR outlet:x = 498 kg/s (17% of mD)
Simplified scheme of RELAP5 model
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
SIMMER-III ANSALDOResults at after 1 hourt = 3600 s: (P = 16 MW)
mC = 2740 kg/s
mD = 2983 kg/s 2985 Kg/s
TCi = 410.5 C
TCo = 449.1 C
TDi = 444.6 C 444 C
TDo = 407.0 C 407 C
y = mC(TDi - TDo)
(TCi - TDo)
x = y + mD - mC
y = 255 kg/s
Recirculation ratio at DHR outlet:x = 498 kg/s (17% of mD)
Simplified scheme of RELAP5 model
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
xy
mC
mD
TCi
TCo
TDo
TDi
TDi
TCi
TCo
TCi
TCo
Figure Source: G. Bandini, P. Meloni, M. Polidori (ENEA - Bologna)
The In-vessel Flow Paths during the Decay Heat Removal mode:
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 13
EFIT-Pb Transient Cases Analysed using SIM-ADS
Forschungszentrum KarlsruheTechnik und Umwelt
IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, 2008 14
Conclusions: Status of Deliverable D1.43 How to continue and finalize our EFIT-PB transient anlysis:
1. Some sections are already finished.
2. Each of us needs to write a short text for each transient describing briefly what you did and what you found. Not more than about 1 page per transient by middle of December (15. 12.2008).
3. I will supply to you for each transient the typical frame of the chapter. In your section of that chapter, please insert your text. If you want, you can also insert your figures and tables in the provided format. Important: retain format otherwise we will have chaos in formatting final report.
4. Evaldas and I will collate the various contributions into final chapters for each transient.
5. Evaldas and myself will then finally collate the entire report for your inspection middle of January 2009 .
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