Verification and Validation of Fast Systems with ENDF/B Data
- Argonne National Lab. (ANL), Argonne, IL (United States)
An extensive and systematic verification, validation and data testing effort using diverse Monte Carlo and deterministic methods with ENDF/B data (Versions V.2 and VI.5) is in progress. Methods verification is obtained by comparing independent methods, including continuous-energy Monte Carlo methods using the VIM and MCNP codes and 1D and 2D transport calculations using multigroup cross section sets generated with the ETOE-II/MC-2 system combined with the TWODANT code. Each of these code systems relies on independently processed data libraries. Inter-comparison of these results is used for verification. Further verification is achieved by comparing and plotting the point-wise cross section libraries of VIM and MCNP. Where possible, benchmark models are taken from both the ICSBEP Handbook and the CSEWG Benchmark Specifications. Inter-comparison of these results quantifies the generally small differences between these references. Calculations are repeated with both ENDF/B-V.2 and ENDF/B-VI.5 data. Inter-comparison of these results quantifies their data dependence. Analyses of criticality and reaction rate ratios are used for the validation and data testing. Calculated neutron balances and neutron energy spectra are also obtained and analyzed to explain the observed differences.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 792115
- Report Number(s):
- ANL/RAE/CP-105588; TRN: US0200734
- Resource Relation:
- Conference: 2001 ANS Winter Meeting Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, Reno, NV (United States), 11-15 Nov 2001; Other Information: PBD: 22 Aug 2001
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
BENCHMARKS
CRITICALITY
CROSS SECTIONS
ENERGY SPECTRA
MONTE CARLO METHOD
FAST NEUTRONS
NUCLEAR REACTION KINETICS
TESTING
RADIATION TRANSPORT
VALIDATION
VERIFICATION
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Evaluated Nuclear Data File (ENDF)
VIM
Monte Carlo N-Particle (MCNP)
TWODANT Code
International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook
Cross Section Evaluation Working Group (CSEWG)
GODIVA
JEZEBEL
Calculated-to-Experimental (C/E)
Verification and Validation (V&V)