REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII … · 2009-11-11 · REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG-TERM DISPOSAL

REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG-TERM DISPOSAL

Georgeta Radulescu John Wagner (presenter)Oak Ridge National Laboratory

International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition

Organized by: Nuclear Safety Council of Spain (CSN) and the International Atomic Energy Agency (IAEA)

October 27 – 30, 2009, Cordoba, Spain

Outline

• Overview of the benchmark specification

• Participating organizations, computer codes, and nuclear data

• Results– Decay calculations for selected isotopes– Criticality calculations

• Sensitivity calculations

• Summary Remarks / Observations

2 International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing and Disposition, Cordoba, Spain, Oct 27-30, 2009

3

Overview of the benchmark specification (1/2)

• Purpose– Study the ability of relevant computer codes and associated

nuclear data to predict spent fuel isotopic compositions and corresponding keff values in a cask configuration over the time duration relevant to SNF disposal

• Objective– Improve understanding and confidence in our ability to predict

keff and source terms for timeframes relevant to long-term disposal of SNF

International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing and Disposition, Cordoba, Spain, Oct 27-30, 2009

4

Overview of the benchmark specification (1/2)

• Specification (issued Nov 2008)– http://www.nea.fr/html/science/wpncs/buc/specifications/phase-VII/Phase-VII_BenchmarkSpecification_REV01.pdf

– PWR UO2 discharge fuel compositions for decay calculations• 4.5-wt% 235U initial enrichment and 50 GWd/MTU burnup • Isotopes relevant to burnup credit and public dose as well as their

precursors (113 total isotopes)– Representative cask model for keff calculations

• Borrowed from previous benchmark specifications

• Requested results– Predicted isotopic concentrations for 30 time steps (0 – 1 M yrs)– Predicted keff values for each time step

• Actinide-only (11 total isotopes) fuel compositions• Actinide and fission product (30 total isotopes) fuel compositions


http://www.nea.fr/html/science/wpncs/buc/specifications/phase-VII/Phase-VII_BenchmarkSpecification_REV01.pdf�

Excerpts from benchmark specification






8

Participating Organizations and Computer Codes/Data Used

Country Organization Decay Code Decay Data Library

Criticality Code

Cross-section Data Library

Slovakia VUJE a SCALE 5.1/ ORIGEN-S

ENDF/B-VI and V SCALE 5.1/KENO VI

ENDF/B-V, 44 energy groups (EGs)

USA ORNL b SCALE 6/ ORIGEN-S(CCC-750)

ENDF/B-VI and V SCALE 6/ KENO V.a

ENDF/B-VII.0, continuous energy (CE)

Japan JAEA c ORIGEN2.2UPJ(NEA-1642)

ORLIB33 d MCNP-4C2 JENDL3.3, CE

Sweden E Mennerdahl Systems

SCALE6/ ORIGEN-S

ENDF/B-VI and V SCALE 6/ KENO V.a

ENDF/B-VII.0, CE

Spain DENIM/CSN/ SEA Ingenieriae

ACAB V2008(NEA-1839)

JEFF-3.1 MCNPX-2.5 JEFF-3.1.1, CE

MCNPX-2.4.0 ENDF/B-VI, CE

ACAB V2008 From ORIGEN-S MCNPX-2.5 JEFF-3.1.1, CE

France AREVA-TN DARWIN 2.1 JEF-2.2 CRISTAL V1.0 JEF-2.2, 172 EGsa Nuclear Power Plant Research Institute Trnava Inc, VUJEb Oak Ridge National Laboratoryc Japan Atomic Energy Agency d JNDC FP nuclear data library and JENDL3.3e Additional criticality calculations and analyses were provided by these organizations to be included as an Annex to the final report.


9

Participating Organizations and Computer Codes/Data Used

Country Organization Decay Code Decay Data Library

Criticality Code

Cross-section Data Library

France IRSN a DARWIN 2.0 JEF-2 MORET 5 b JEFF-3.1, CE

PHOENIX 1.0.0a b

DECAY.LIB ( ORGEN2.2 )

N/A N/A

Germany GRS c ORIGEN-X-2008

ENDF/B-VI SCALE 6/ KENO V.a

ENDF/B-VII.0, 238 EGs

Czech Republic

Nuclear Research Institute at Rez

SCALE 6/ ORIGEN-S

ENDF/B-VI and V

SCALE 6/ KENO V.a

ENDF/B-VII.0, 238 EGs

SCALE 6/ KENO V.a

ENDF/B-VII.0, CE

Finland VTT d SCALE 6/ ORIGEN-S

ENDF/B-VI and V

MCNP5, version 1.40

ENDF/B-VI, CE

Hungary KFKI e SCALE 6/ ORIGEN-S

ENDF/B-VI and V

MCNP5 ENDF/B-VI.2 and V, CE

TIBSO(NEA-1592)

JEF-2.2 MCNP5 ENDF/B-VI.2 and V, CE

a Institut de Radioprotection et de Sûreté Nucléaireb Under developmentc Gesellschaft für Anlagen-und Reaktorsicherheit mbHd VTT Technical Research Centre of Finlande KFKI Atomic Energy Research Institute


Summary: Participation

• 11 countries, 13 organizations, 14 decay calculations, 15 criticality calculations• ORIGEN, ORIGEN-based, DARWIN, PHOENIX decay calculation codes

– Numerical and analytical methods for solving decay chain equations• Matrix exponential method (ORIGEN, PHOENIX)• Analytical method and 4th order Runge Kutta numerical method (DARWIN, PHOENIX)

– Decay data libraries• ENDF/B-V, VI• JENDL3.3• JEFF-3.1• JEF-2.2

• SCALE, MCNP, MORET Monte Carlo criticality codes– Neutron cross-section data libraries

• ENDF/B-V, 44 energy groups• ENDF/B-VI continuous energy• ENDF/B-VII.0 continuous energy• ENDF/B-VII.0 238 energy groups• JEF-2.2, 172 energy groups• JENDL3.3 continuous energy• JEFF-3.1 continuous energy• JEFF-3.1.1 continuous energy


ISOTOPIC RESULTS

International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing and Disposition, Cordoba, Spain, Oct 27-30, 2009 11

Time-dependent Actinide Concentrations


14

Comparison of Decay Calculation Results for U-233

Note: ORIGEN-X-2008 results were obtained using 3 different runs and were affected by the choice of one big time step for the beginning of the second (150 years) and third (20,000 years) runs.


15



16

Comparison of Decay Calculation Results for Pu-241

241Pu (14.4y) → 241Am (432.7y)241Pu result variability for the first 200 years after fuel discharge indicates differences in 241Pu half-life values.


Time-dependent FP Concentrations


18

Comparison of Decay Calculation Results for Sm-151

Note: Different trends between the results obtained with JEF and JENDL decay libraries (DARWIN, TIBSO, and ORIGEN2.2UPJ) and the other results.


19

Comparison of Decay Calculation Results for Eu-151

Note: Different trends between the results obtained with JEF and JENDL decay libraries (DARWIN, TIBSO, and ORIGEN2.2UPJ) and the other results. 151Sm (90y) → 151Eu.


20

Comparison of Decay Calculation Results for Gd-155

Note: DARWIN, TIBSO, and PHONIX 1.0.0a beta results are lower than the results of the other calculations for short decay times. 155Eu (4.75 y) →155Gd.


CRITICALITY RESULTS


keff Values – difference from mean


-0,008

-0,006

-0,004

-0,002

0,000

0,002

0,004

0,006

0,008

1 3 5 7 9 11 13 15

Fresh Fuel: Mean=1.1481; StdDev=0.0031

Act: Mean=0.9551; StdDev=0.0025

Act + FP: Mean=0.8610; StdDev=0.0021

1: SCALE 5.1 (ENDF/B-V, 44EGs)2: SCALE 6 (ENDF/B-VII.0, CE)3: MCNP-4C2 (JENDL3.3)4: SCALE6 (ENDF/B-VII.0, CE)5: MCNPX-2.5 (JEFF-3.1.1, CE)6: MCNPX-2.4.0 (ENDF/B-VI, CE)7: MCNPX-2.5 (JEFF-3.1.1, CE)8: CRISTAL V1.0 (JEF 2.2, 172 EGs)9: MORET 5 (JEFF-3.1)10: SCALE 6 (ENDF/B-VII.0, 238 EGs)11: SCALE 6 (ENDF/B-VII.0, 238 EGs)12: SCALE 6 (ENDF/B-VII.0, CE)13: MCNP5 V1.40 (ENDF/B-VII, CE)14: MCNP5 (ENDF/B-VI.2, CE)15: MCNP5 (ENDF/B-VI.2, CE)

23

keff as a Function of Decay Time for Actinide-only Fuel Compositions

Actinide-only Fuel Compositions

0.84

0.85

0.86

0.87

0.88

0.89

0.9

0.91

0.92

0.93

0.94

0.95

0.96

1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06

Decay Time (years)

keff

SCALE 5.1/KENO VI (ENDF/B-V, 44 EGs)

SCALE 6/KENO V.a (ENDF/B-VII.0, CE)

MCNP-4C2 (JENDL3.3)


MCNPX-2.5 (JEFF-3.1.1, CE); ACAB (JEFF-3.1)

MCNPX-2.4.0 (ENDF/B-VI); ACAB (JEFF-3.1)

MCNPX-2.5 (JEFF-3.1.1, CE); ACAB (ORIGEN-S)

CRISTAL V1.0 (JEF 2.2, 172 EGs)

MORET 5 (JEFF-3.1)

SCALE 6/KENO V.a (ENDF/B-VII.0, 238 EGs)



MCNP5 V1.40 (ENDF/B-VI, CE)

MCNP5 (ENDF/B-VI.2, CE); ORIGEN-S

MCNP5 (ENDF/B-VI.2, CE); TIBSO


24

keff Result Variability as a Function of Decay Time

Actine-only Fuel Compositions

-1.00%

-0.80%

-0.60%

-0.40%

-0.20%

0.00%

0.20%

0.40%

0.60%

0.80%

1.00%

1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06

Decay Time (years)

(kef

f -

keff

_ave

rag

e)/k

eff_

aver

age

(%)



MCNP-4C2 (JENDL3.3)






MORET 5 (JEFF-3.1)





MCNP5 (ENDF/B-VI.2 and V, CE); ORIGEN-S

MCNP5 (ENDF/B-VI.2 and V, CE); TIBSO

Δkeff-min = 0.0062 (150 years)Δkeff-max = 0.0153 (1,000,000 years)


Actinide-only keff Values – Mean and Standard Deviation as a Function of Decay Time


0,0000

0,0005

0,0010

0,0015

0,0020

0,0025

0,0030

0,0035

0,0040

0,0045

0,8400

0,8600

0,8800

0,9000

0,9200

0,9400

0,9600

0,01 0,1 1 10 100 1000 10000 100000 1000000

keff

26

keff as a Function of Decay Time for Actinide and FP Fuel Compositions

Actinide and FP Fuel Compositions

0.73

0.74

0.75

0.76

0.77

0.78

0.79

0.8

0.81

0.82

0.83

0.84

0.85

0.86

1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06

Decay Time (years)

keff



MCNP-4C2 (JENDL3.3)






MORET 5 (JEFF-3.1)





MCNP5 (ENDF/B-VI.2, CE)

MCNP5 (ENDF/B-VI.2, CE)


27

keff Result Variability as a Function of Decay Time

Actine and FP Fuel Compositions

-1.20%

-1.00%

-0.80%

-0.60%

-0.40%

-0.20%

0.00%

0.20%

0.40%

0.60%

0.80%

1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06

Decay Time (years)

(kef

f - k

eff_

aver

age)

/kef

f_av

erag

e (%

)



MCNP-4C2 (JENDL3.3)






MORET 5 (JEFF-3.1)





MCNP5 (ENDF/B-VI.2 and V, CE); ORIGEN-S

MCNP5 (ENDF/B-VI.2 and V, CE); TIBSO

Δkeff-min = 0.0059 (20 and 40 years)Δkeff-max = 0.0112 (45,000 years)


Cross-section Data Sensitivity and Uncertainty Analysis

ENDF/B-VII Neutron Cross-Section DataActinide and Fission Product Compositions


SCALE/TSUNAMI Cross-section Sensitivity and Uncertainty Analysis

• SCALE ENDF/B-VII 238 energy-group library• Covariance data from ENDF/B-VII, ENDF/B-VI and

JENDL3.3 • Energy and region integrated keff sensitivity to total and

reaction-specific cross section (sensitivity coefficient)

• keff uncertainty due to cross-section covariance data

nx

nx

effeff,k /

k/kS n

x ΣΣδ

δΣ =


keff Sensitivity to ENDF/B-VII Cross-section Data for Actinides


keff Sensitivity to ENDF/B-VII Cross-section Data for FPs


keff Uncertainty Due to Cross-section Covariance Data


Main Contributions to keff Uncertainty: 5-Year Composition


Main Contributions to keff Uncertainty: 100-Year Composition


Main Contributions to keff Uncertainty: 100,000-Year Composition


Summary Remarks / Observations


Summary: Participation • 11 countries, 13 organizations, 14 decay calculations, 15 criticality calculations• ORIGEN, ORIGEN-based, DARWIN, PHOENIX decay calculation codes

– Numerical and analytical methods for solving decay chain equations• Matrix exponential method (ORIGEN, PHOENIX)• Analytical method and 4th order Runge Kutta numerical method (DARWIN, PHOENIX)

– Decay data libraries• ENDF/B-V, VI• JENDL3.3• JEFF-3.1• JEF-2.2

• SCALE, MCNP, MORET Monte Carlo criticality codes– Neutron cross-section data libraries

• ENDF/B-V, 44 energy groups• ENDF/B-VI continuous energy• ENDF/B-VII.0 continuous energy• ENDF/B-VII.0 238 energy groups• JEF-2.2, 172 energy groups• JENDL3.3 continuous energy• JEFF-3.1 continuous energy• JEFF-3.1.1 continuous energy


39

Preliminary Observations: Decay Calculations

• Several different trends identified– Different trends between the results obtained with JENDL and

ORIGEN2 DECAY.LIB data libraries (ORIGEN2.2UPJ and PHOENIX 1.0.0a) and the other results for

• 239Pu, 240Pu, 242Pu, 242mAm– Different trends among the results obtained with different libraries for

• 241Pu, 243Am– Different trends between the results obtained with JEF and JENDL

decay data libraries (DARWIN, TIBSO, and ORIGEN2.2UPJ) and the other results for

• 151Sm, 151Eu– Different trends between the results obtained with JEF and ORIGEN2

DECAY.LIB data libraries (DARWIN, TIBSO, and PHOENIX 1.0.0a) and the other results for

• 155Gd (155Eu)


40

Preliminary Observations: Criticality Calculations

• keff calculations were performed using a variety of criticality codes and cross-section data

• Results for specified compositions provide insights into variations due to criticality code and cross-section data– Fresh fuel composition

• keff varied from 1.1429 ± 0.0008 (SCALE 5.1, ENDF/B-V 44 EGs) to 1.1540 ± 0.0003 (CRISTAL V1.0, JEF-2.2, 172 EGs)

– Discharge actinide-only fuel composition• keff varied from 0.9507 ± 0.0004 (SCALE 6, ENDF/B-VII.0 CE) to 0.9582 ±

0.0003 (MCNPX-2.5, JEFF-3.1.1 CE)– Discharge actinide and FP fuel composition

• keff varied from 0.8568 ± 0.0003 (SCALE 6, ENDF/B-VII.0 CE) to 0.8639 ±0.0005 (MCNP-4C2, JENDL3.3 CE)


41

Preliminary Observations: Criticality Calculations

• keff results for time-dependent compositions show the impact of nuclear data, calculation method, and isotopic composition bias

• Computational method and cross-section data appear to have a larger impact on keff than differences in isotopic composition predictions

• keff results for time-dependent actinide-only compositions• Δkeff-min = 0.0062 (150 years)• Δkeff-max = 0.0153 (1,000,000 years)

• keff results for time-dependent actinide and FP compositions• Δkeff-min = 0.0059 (20 and 40 years)• Δkeff-max = 0.0112 (45,000 years)

• keff uncertainty due to covariance data• Min %Δkeff/ keff = 0.4845 (100,000 years)• Max %Δkeff/ keff = 0.7601 (100 years)


Next steps

• Complete analysis of participant’s results• Communicate with participants about their results,

as needed

• Perform sensitivity calculations for isotopic predictions

• Complete and circulate draft report to participants for review

• Propose follow-up activity, if identified• Publish benchmark report


Backup Slides


44



45

Comparison of Decay Calculation Results for Np-237

241Pu (14.4y) → 241Am (432.7y) → 237Np (2.14E6y)


46



47


Note: Different trends between ORIGEN2.2UPJ and PHONIX 1.0.0a beta results and the results of the other calculations for long decay times.


48




49

Comparison of Decay Calculation Results for Am-241


241Pu (14.4y) → 241Am (432.7y)

50

Comparison of Decay Calculation Results for Am-242m



51

Comparison of Decay Calculation Results for Am-243


52

Comparison of keff Values for the Fresh Fuel Composition

Fresh Fuel Composition

1.14

1.142

1.144

1.146

1.148

1.15

1.152

1.154

1.156

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15

Criticality Calculation No.

keff

1: SCALE 5.1 (ENDF/B-V, 44EGs)2: SCALE 6 (ENDF/B-VII.0, CE)3: MCNP-4C2 (JENDL3.3)4: SCALE6 (ENDF/B-VII.0, CE)5: MCNPX-2.5 (JEFF-3.1.1, CE)6: MCNPX-2.5 (ENDF/B-VI, CE)7: MCNPX-2.5 (JEFF-3.1.1, CE)8: CRISTAL V1.0 (JEF 2.2, 172 EGs)9: MORET 5 (JEFF-3.1)10: SCALE 6 (ENDF/B-VII.0, 238 EGs)11: SCALE 6 (ENDF/B-VII.0, 238 EGs)12: SCALE 6 (ENDF/B-VII.0, CE)13: MCNP5 V1.40 (ENDF/B-VI, CE)

keff-max – keff-min = 0.01109


53

Comparison of keff Values for Discharge Actinide-only Fuel Composition

Discharge Actinide-only Fuel Composition

0.95

0.951

0.952

0.953

0.954

0.955

0.956

0.957

0.958

0.959

0.96

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15


keff

1: SCALE 5.1 (ENDF/B-V, 44EGs)2: SCALE 6 (ENDF/B-VII.0, CE)3: MCNP-4C2 (JENDL3.3)4: SCALE6 (ENDF/B-VII.0, CE)5: MCNPX-2.5 (JEFF-3.1.1, CE)6: MCNPX-2.4.0 (ENDF/B-VI, CE)7: MCNPX-2.5 (JEFF-3.1.1, CE)8: CRISTAL V1.0 (JEF 2.2, 172 EGs)9: MORET 5 (JEFF-3.1)10: SCALE 6 (ENDF/B-VII.0, 238 EGs)11: SCALE 6 (ENDF/B-VII.0, 238 EGs)12: SCALE 6 (ENDF/B-VII.0, CE)13: MCNP5 V1.40 (ENDF/B-VI, CE)14: MCNP5 (ENDF/B-VI.2, CE)15: MCNP5 (ENDF/B-VI.2, CE)



54

Comparison of keff Values for Discharge Actinide and FP Fuel Composition

Discharge Actinide and Fission Product Fuel Composition

0.856

0.857

0.858

0.859

0.86

0.861

0.862

0.863

0.864

0.865

0.866

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15


keff

1: SCALE 5.1 (ENDF/B-V, 44EGs)2: SCALE 6 (ENDF/B-VII.0, CE)3: MCNP-4C2 (JENDL3.3)4: SCALE6 (ENDF/B-VII.0, CE)5: MCNPX-2.5 (JEFF-3.1.1, CE)6: MCNPX-2.4.0 (ENDF/B-VI, CE)7: MCNPX-2.5 (JEFF-3.1.1, CE)8: CRISTAL V1.0 (JEF 2.2, 172 EGs)9: MORET 5 (JEFF-3.1)10: SCALE 6 (ENDF/B-VII.0, 238 EGs)11: SCALE 6 (ENDF/B-VII.0, 238 EGs)12: SCALE 6 (ENDF/B-VII.0, CE)13: MCNP5 V1.40 (ENDF/B-VI, CE)14: MCNP5 (ENDF/B-VI.2, CE)15: MCNP5 (ENDF/B-VI.2, CE)



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REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII … · 2009-11-11 · REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG-TERM DISPOSAL