GRS Results for the Burnup Pin-cell Benchmark Propagation of Cross-Section, Fission Yields and Decay Data Uncertaintie

Cabellos de Francisco, Oscar Luis

Gallner, L.

Martinez, J.S.

Puente Espel, F.

Zwermann, W.

Archivo Digital UPM

GRS Results for the Burnup Pin-cell Benchmark Propagation of Cross-Section, Fission Yields and Decay Data Uncertainties

Servicio de Coordinación de Bibliotecas de la Universidad Politécnica de Madrid

UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
GRS Results for the Burnup Pin-cell Benchmark
Propagation of Cross-Section, 
Fission Yields and Decay Data Uncertainties
J.S. Martinez (1, 2) , W. Zwermann (1) ,
L. Gallner (1) , F. Puente-Espel (1)  and O. Cabellos (2)
(1) Gesellschaft für Anlagen- und Reaktorsicherheit 
(GRS) mbH, Munich, Germany
(2) Department of Nuclear Engineering, 
Universidad Politécnica de Madrid, Spain
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
Outline
1. Introduction
1.1 the XSUSA Methodology
1.2 Extension to Fission Yields and Decay Data
2. Problem and Results
2.1 Description of the Burnup Pin-cell Benchmark 
2.2 Impact on k-eff of Cross-Sections, Fission Yields and Decay Data Uncertainties
2.3 Impact on Isotopic Evolution 
3. Conclusions and future work
2
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
1. Introduction: the XSUSA Methodology
- Influence of Engineering Parameters and Cross-Section Uncertainties
- Many calculations (typically >> 100) are run for the same problem with varied input data
- Variations are generated randomly from the probability distributions of the input parameters and 
   correlations between them
- Output quantities are statistically analyzed, uncertainty ranges and sensitivities are determined
- Applications: Critical experiments. 
Transport calculations: multiplication factors, fission rate distributions
Full core calculations.
MC and nodal diffusion: multiplication factors, power distributions 
  Coupled nodal diffusion + thermo-hydraulics. 
Fuel assembly depletion calculations. 
Multiplication factors, cross-sections, fission rates, nuclide inventories...
- XSUSA: Uncertainties through the generation of varied inputs and  Cross-Sections (XS) and
  repeated simulation. Fission Yields (FY) and Decay Data (DD) uncertainties not propagated
3
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
ORIGEN-S NEWT
XS, fluxes  
Regarding depletion calculations, XSUSA has been dealing with cross-section uncertainties
BUT missing the contribution coming from the temporal evolution of the nuclide inventory
- Accurate Burnup Simulation: Coupling between DEPLETION and TRANSPORT calculations
Isotopic Content Changes → Reaction Rates Changes  
 
Neutron Cross-Section 
Data Libraries 
& Uncertainties
Fission Yields 
Decay Data Libraries 
& Uncertainties 
IMPACT ?IMPACT ?
Varied XS libs
Repeated Simulations
Statistics
Varied FY & DD libs
Repeated Simulations
Statistics
 Which is the impact on nuclear calculations of uncertainties coming from 
decay data, fission yields and cross-sections when considered independently and altogheter ?
4
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
λ
γ
λ
γ
ORIGEN-S
ASCII libs.
ENDF/B-VII.1
decay lib.
ENDF/B-VII.1
Fission Yields lib.
ORIGEN-S
1. Introduction: Extension to Fission Yields and Decay Data
- XSUSA is updated to propagate uncertainties in Fission Yields and Decay Data
- XSUSA package includes two codes that generate pools of varied FY and DD libraries beforehand
- We vary the ORIGEN-S FY and DD libraries (ASCII files) respecting the information they contain 
(no additions, no replacements) according to the corresponding uncertainties found in ENDF/B-VII.1 
through a gaussian sampling (MEDUSA) around the nominal values in ORIGEN-S libraries   
γ*
. . .
γ* γ*
λ* λ* λ*. . .
POOL of 1000 O-S ASCII 
varied yields libs.
POOL of 1000 O-S ASCII 
varied decay libs.
5
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
YiSaB: XSUSA Yields Sampling Branch DeSaB: XSUSA Decay Sampling Branch
  
 
λγ ENDF/B-VII.1
decay lib.
ENDF/B-VII.1
yields libs.
γ, Δγ λ, Δλbr, Δbr
MEDUSA
input
MEDUSA
input
MEDUSA MEDUSA
γ* → 1000 λ*, br* → 1000MEDUSA outputMEDUSA output
Compatibility test Compatibility testλγORIGEN-SASCII lib
ORIGEN-S
ASCII lib
λ*γ* λ*γ*
. . .. . .
γ* γ* γ* λ* λ* λ*
POOL of 1000 O-S ASCII varied yields libs. POOL of 1000 O-S ASCII varied decay libs.
6
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
2. Problem and Results: Description of the Burnup Pin-cell Benchmark
- The UAM-6 Burnup Pincell Benchmark (*) Irradiation Characteristics
- simple pincell 4.85 % enrichment
- burnt at a constant power of 33.58 MW/MTU 
- during 1825 days to a burnup of 61.28 GWd/MTU
- total decay time: 300 years
Data requested (at different time-steps)
- k-inf uncertainties
Main nuclide reactions contributions +
contribution of chi, nu-bar and others
- Reaction rates and uncertainties for major isotopes
  - capture for U235,238 and Pu239,240,241
  - fission for U235,238 and Pu239, 240,241
  - two-group macroscopic cross sections and 
    uncertainties for thehomogenized pin-cell
    absorption, fission, nu-fission and diffusion
- Nuclide concentrations (15 Acts + 36 FPs)
Unit cell pitch (mm) 14.427
Fuel pellet diameter (mm) 9.391
Fuel pellet material UO2
Fuel density (g/cm3) 10.283
Fuel enrichment (w/o) 4.85
Cladding outside diameter (mm) 10.928
Cladding thickness (mm) 0.673
Cladding material Zircaloy-4
Cladding density (g/cm3) 6.55
Gap material He
Moderator material H2O
Fuel temperature (K) 900.0
Cladding Temperature (K) 600.0
Moderator (coolant) temperature (K) 562.0
Moderator (coolant) density (g/cm3) 0.7484
Reactor Power (MWt) 2772.0
Total number of fuel assemblies 177
Number of fuel rods per fuel assembly 208
Active core length (mm) 3571.20
* BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR DESIGN, OPERATION AND SAFETY ANALYSIS OF LWRs, 
Addition to V.I: Specification and Support Data for the Neutronics Cases (Phase I) “PWR Burnup Pin-Cell Benchmark” O. Cabellos and K.Ivanov
7
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
Objectives
- Application of the extended XSUSA methodology to a simple test as a proof of principle
- Assessment of the impact on k-eff and the isotopic evolution of the independent and joint propagation 
  of the different nuclear data uncertainties: XS, FY and DD
Simulations performed 
- Generation of 1000 of varied Fission Yields libraries and 1000 of varied Decay Data libraries
- Nominal calculation based on the original unchanged libraries 
         Impact of DD → 1000 Burnup Calculations
         FY  →  ''
         XS  →  ''
   XS + FY + DD →   ''
Data Analyzed
- k-eff at EOB. Total Uncertainty and contribution from the different uncertainty sources
- Nuclide concentrations, uncertainties and contributions
- Comparison to the the results provided by other institutions 
8
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
0 100 200 300 400 500 600 700 800 900 1000
0,87
0,88
0,89
0,9
0,91
0,92
Nominal k-eff k-eff [DD]
Simulations
k-eff
Nominal k-eff Averaged k-eff Uncertainty (%)
0.895883 0.895853 0.001
9
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
0 100 200 300 400 500 600 700 800 900 1000
0,87
0,88
0,89
0,9
0,91
0,92
Nominal k-eff k-eff [FY] Mean [FY]
Upper Lower k-eff [DD]
Simulations
k-eff
Nominal k-eff Averaged k-eff Uncertainty (%)
0.895883 0.896009 0.376
10
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
0 100 200 300 400 500 600 700 800 900 1000
0,87
0,88
0,89
0,9
0,91
0,92
Nominal k-eff mean [XS] Upper Lower
k-eff [XS] k-eff [FY] k-eff [DD]
Simulations
k-eff
Nominal k-eff Averaged k-eff Uncertainty (%)
0.895883 0.896135 0.764
11
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
0 100 200 300 400 500 600 700 800 900 1000
0,87
0,88
0,89
0,9
0,91
0,92
Nominal k-eff mean [XS+FY+DD] Upper Lower
k-eff [XS+FY+DD] k-eff [XS] k-eff [FY] k-eff [DD]
Simulations
k-eff
Nominal k-eff Averaged k-eff Uncertainty (%)
0.895883 0.896229 0.841
12
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
0,0
0
0,3
0
1,5
0
3,5
0
5,5
0
7,5
0
9,5
0
13
,00
17
,00
22
,50
32
,50
42
,49
52
,50
60
,64
0,00%
0,10%
0,20%
0,30%
0,40%
0,50%
0,60%
0,70%
0,80%
0,90%
XS FY DD XS+FY+DD
K-eff uncertainty finds its major contributor in XS > FY > DD (negligible) all over the irradiation
13
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
Col.
Parm. Var. 0 
GWd/MTU
10 
GWd/MTU
20 
GWd/MTU
30 
GWd/MTU
40 
GWd/MTU
50 
GWd/MTU
60 
GWd/MTU
shutdown
UPM Nom 1,4045 1,2461 1,1581 1,0837 1,0167 0,9560 0,9030
Uncert Xs. 0.49% 0.51% 0.57% 0.63% 0.68% 0.74% 0.79%
GRS Nom 1,4029 1,2474 1,1623 1,0913 1,0270 0,9688 0,9169 0,9102
Uncert Xs 0,48% 0,49% 0,55% 0,60% 0,65% 0,70% 0,75% 0,75%
FY 0,0% 0,17% 0,21% 0,28% 0,32% 0,36% 0,37% 0,38%
Tot. 0,48% 0,51% 0,58% 0,67% 0,73% 0,79% 0,84% 0,84%
NRG Nom 1,41 1,25 1,16 1,08 1,02 0,955 0,901
Uncert U-235 0,50% 0,44% 0,39% 0,35% 0,32% 0,28% 0,24%
U-238 0,46% 0,48% 0,45% 0,40% 0,35% 0,33% 0,36%
Pu-239 0,05% 0,15% 0,26% 0,33% 0,39% 0,44% 0,47%
L FPs 0,05% 0,37% 0,36% 0,32% 0,23% 0,29% 0,28%
FY 0,05% 0,18% 0,19% 0,21% 0,21% 0,19% 0,17%
Tot. 0,68% 0,79% 0,78% 0,76% 0,76% 0,76% 0,79%
14
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  15
  0 GWd/MTU 10 GWd/MTU 30 GWd/MTU 60 GWd/MTU
  mean mean rel. std. dev. mean rel. std. dev. mean rel. std. dev.
∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs
U-234 UPM 1.17E-05 1.03E-05 1.0 0.0  - 7.94E-06 1.9 0.0  - 5.04E-06 3.1 0.0  -
 NRG 1.17E-05 1.03E-05 0.1   7.92E-06 0.4   4.97E-06 0.9   
 GRS 1.13E-03 8.72E-04 0.8 0.0  0.02 4.98E-04 2.6  0.0  0.09 1.74E-04 5.7 0.0   0.30
U-235 UPM 1.13E-03 8.71E-04 0.2 0.0  - 4.97E-04 0.3 0.0  - 1.74E-04 0.6 0.0  -
 NRG 1.13E-03 8.75E-04 0.2   5.02E-04 0.7   1.75E-04 2.8   
 GRS 0.00E+00 4.87E-05 0.1  0.0   0.01 1.15E-04 0.5  0.0  0.06 1.58E-04 1.9  0.0 0.35 
U-238 UPM 2.18E-02 2.17E-02 0.0 0.0  - 2.14E-02 0.1 0.0  - 2.08E-02 0.1 0.0  -
 NRG 2.18E-02  2.17E-02 0.0  2.14E-02 0.0   2.08E-02 0.0     
 GRS 0.00E+00 4.87E-05 0.01 0.0   0.0 1.15E-04 0.02 0.0  0.06 1.58E-04 0.04  0.0  0.35
Pu-238 UPM 0.00E+00 1.24E-07 2.3 0.0  - 2.08E-06 1.4 0.0  - 1.07E-05 0.9 0.0  -
 NRG 0.00E+00 1.22E-07 12.1   2.15E-06 5.0   1.14E-05 2.7   
 GRS 0.00E+00 8.07E-05 7.6 0.0 0.2 1.45E-04 4.4  0.0  0.24 1.57E-04 0.04 0.0 0.32 
Pu-239 UPM 0.00E+00 8.08E-05 1.2 0.0  - 1.46E-04 1.1 0.0  - 1.60E-04 1.3 0.0  -
 NRG 0.00E+00 7.78E-05 1.8   1.40E-04 2.3   1.53E-04 3.2   
 GRS 0.00E+00 9.36E-06 1.2  0.0 0.1 4.00E-05 1.5  0.0 0.2 7.53E-05 2.0  0.0  0.46
Pu-240 UPM 0.00E+00 9.36E-06 3.1 0.0  - 4.01E-05 2.1 0.0  - 7.59E-05 1.9 0.0  -
 NRG 0.00E+00 9.09E-06 1.9   3.89E-05 2.0   7.39E-05 2.4   
 GRS 0.00E+00 3.55E-06 1.6  0.0 0.07 2.47E-05 1.9 0.0 0.11 4.67E-05 2.2 0.0 0.27 
Pu-241 UPM 0.00E+00 3.55E-06 2.9 0.0  - 2.46E-05 1.7 0.0  - 4.68E-05 1.5 0.0  -
 NRG 0.00E+00 3.42E-06 2.0   2.42E-05 1.5   4.59E-05 2.2   
 GRS 0.00E+00 1.98E-07 1.6 0.0  0.16 4.96E-06 1.4 0.0 0.16 2.33E-05 1.8 0.0  0.32
Pu-242 UPM 0.00E+00 1.98E-07 3.7 0.0  - 4.95E-06 1.9 0.0  - 2.31E-05 1.4 0.0  -
 NRG 0.00E+00 1.92E-07 3.0   4.98E-06 1.9   2.40E-05 1.4   
 GRS 0.00E+00 1.98E-07 2.0 0.0 0.14 4.96E-06 2.3 0.0  0.10 2.33E-05 3.6 0.0  0.21
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  16
  0 GWd/MTU 10 GWd/MTU 30 GWd/MTU 60 GWd/MTU 
  mean mean rel. std. dev. mean rel. std. dev. mean rel. std. dev.
∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs
Gd-155 UPM 0.00E+00 5.06E-10 12.4 0.2 5.1 2.23E-09 15.2 0.2 2.4 5.80E-09 15.4 0.2 1.1
 NRG 0.00E+00 5.06E-10 27.0   2.30E-09 22.4   6.02E-09 22.8   
 GRS 0.00E+00 1.56E-07 4.9  0.27  15 1.34E-06 6.0   0.24  9.8 7.63E-06 5.3   0.20 8.8 
UPM: ∆N due to ∆XS, ∆FYs and ∆DD
GRS: ∆N due to ∆XS, ∆FYs and ∆DD
NRG: ∆N due to ∆XS+FYs
Nd-143 UPM 0.00E+00 1.23E-05 0.6 0.0 2.6 3.23E-05 0.5 0.0 1.4 4.79E-05 0.5 0.0 1.1
 NRG 0.00E+00 1.21E-05 4.4   3.20E-05 4.9   4.72E-05 6.6   
 GRS 0.00E+00 9.11E-06 0.3  0.05  3.9 2.46E-05 0.9  0.03 4.5 4.20E-05 2.1  0.03 5.9 
Nd-145 UPM 0.00E+00 9.10E-06 0.7 0.0 2.8 2.46E-05 0.5 0.0 1.6 4.18E-05 0.5 0.0 1.1
 NRG 0.00E+00 9.05E-06 4.9   2.48E-05 6.7   4.28E-05 10.9   
 GRS 0.00E+00 7.53E-06 0.3  0.0  4.6 2.35E-05 1.0  0.0 5.2 5.05E-05 2.0  0.0 6.7 
Nd-148 UPM 0.00E+00 4.20E-06 0.7 0.0 2.1 1.24E-05 0.5 0.0 1.3 2.45E-05 0.4 0.0 0.9
  NRG  -  -     -     -    
 GRS 0.00E+00 1.76E-06 0.3  0.0  16.5 5.58E-06 0.3  0.0 14.5 1.18E-05 0.4  0.0 13 
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  17
  0 GWd/MTU 10 GWd/MTU 30 GWd/MTU 60 GWd/MTU
  mean mean rel. std. dev. mean rel. std. dev. mean rel. std. dev. 
∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs ∆XS ∆DD ∆FYs
Sm-149 UPM 0.00E+00 1.17E-07 14.0 0.0 6.4 1.21E-07 14.3 0.0 5.7 1.05E-07 15.5 0.0 5.1
 NRG 0.00E+00 1.09E-07 11.4  0.0  1.15E-07 10.8  0.3  9.97E-08 11.3  0.3  
 GRS 0.00E+00 2.76E-06 1.7   10.1 9.28E-06 2.0   9.5 1.91E-05 2.5   10.6
Sm-152 UPM 0.00E+00 1.30E-06 1.0 0.0 1.9 3.47E-06 1.2 0.0 1.3 5.26E-06 1.6 0.0 0.9
 NRG 0.00E+00 1.25E-06 16.2   3.47E-06 13.3   5.37E-06 11.7   
 GRS 0.00E+00 2.51E-07 0.8 0.0 15.2 9.61E-07 1.8 0.1 11.3 2.41E-06 2.9 0.1 8.8 
UPM: ∆N due to ∆XS, ∆FYs and ∆DD
GRS: ∆N due to ∆XS, ∆FYs and ∆DD
NRG: ∆N due to ∆XS+FYs
Cs-133 UPM 0.00E+00 1.55E-05 0.7 0.0 2.0 4.36E-05 0.5 0.0 1.1 7.63E-05 0.4 0.0 0.9
 NRG 0.00E+00 1.50E-05 3.5   4.25E-05 3.7   7.48E-05 5.4   
 GRS 0.00E+00 4.79E-07 0.2  0.0 3.2 3.72E-06 0.5  0.0 1.7 1.15E-05 1.2  0.0  1.7
Cs-137 UPM 0.00E+00 1.51E-05 0.7 0.1 2.6 4.43E-05 0.5 0.0 1.6 8.59E-05 0.4 0.0 1.2
 NRG 0.00E+00 1.49E-05 2.2   4.42E-05 2.0   8.62E-05 2.1   
 GRS 0.00E+00 1.54E-05 0.0  0.2  1.9 4.47E-05 0.0  0.2 1.7 8.59E-05 0.0  0.2 1.7 
Mo-95 UPM 0.00E+00 8.36E-06 1.0 0.0 9.7 3.55E-05 0.7 0.0 6.8 6.90E-05 0.5 0.0 4.8
 NRG 0.00E+00 8.28E-06 4.9   3.56E-05 5.8   6.97E-05 7.6   
 GRS 0.00E+00 1.48E-05 0.1  0.1  5.2 4.15E-05 0.2  0.1 6 7.41E-05 0.4  0.1 7.9 
Tc-99 UPM 0.00E+00 1.47E-05 0.7 0.0 2.6 4.15E-05 0.5 0.0 1.6 7.44E-05 0.4 0.0 1.3
 NRG 0.00E+00 1.42E-05 10.4   4.08E-05 9.4   7.39E-05 9.1   
 GRS 0.00E+00 1.29E-05 0.1  0.0  11.2 3.84E-05 0.2  0.01 9.9 7.47E-05 0.4  0.1  9.5
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
IN SHORT
- The GRS / XSUSA methodology accounts for cross-sections and engineering uncertainties.
   Now, in addition, it takes into account fission yields and decay data uncertainties from ENDF-6 libs.
- Tools to generate pools of varied libraries for ORIGEN-S have been developed (YiSaB and DeSaB) 
  and their outputs are used following the XSUSA method of repeated calculations 
- The XSUSA extended capabilities have been applied to the UAM-6 burnup pincell benchmark.
On k-eff: low impact from decay data uncertainties, Xs main contributors to its uncertainty
On inventory: depending on the nuclide, fission yields and cross-section uncertainties  
FUTURE WORK
- Integration of YiSaB and DeSaB within the XSUSA flow chart so they generate libraries on the fly
- Application of the methodology to complex problems
-  Inclusion of correlations to be taken into account in the MEDUSA sampling of the fission yields 
   (GRS – ORNL collaboration)  
   
18
UAM-7 Workshop, Issy-les-Moulineaux, France, April 10-12, 2013  
Questions? 
Thank you very much for your attention
Questions?  
   


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GRS Results for the Burnup Pin-cell Benchmark Propagation of Cross-Section, Fission Yields and Decay Data Uncertainties

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