Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

An Analysis of the HEW-MET-FAST-035 Problem Using CENTRM and SCALE

Conference ·
OSTI ID:7466
 [1];  [2]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division; ORNL
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
+ Show Author Affiliations

An U/Fe benchmark, designated as HEU-MET-FAST-035, has been approved for inclusion in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. The SCALE code and cross sections performed poorly in calculating this critical experiment. Deficiencies in both the ENDF/B-V representation of the resonance region for Fe and in the Nordheim integral treatment when applied to Fe were identified. The combination of these deficiencies led to an almost 10% over-prediction of keff. Problems involving a large percentage of Fe and intermediate-energy spectrums present special cross-section processing difficulties for SCALE. In ENDF/B-V, resonance data for Fe only go to 400 keV, although resonances are present well above 1 MeV. Significant resonance data are stored as file 3 data instead of as resonance parameters. The Nordheim Integral Treatment used in NITAWL to process cross sections assume: resonances are widely spaced and all relevant information is contained in the resonance parameters (file 3 data is not processed). These limitations and assumptions result in poor solutions for this class of problems.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-96OR22464
OSTI ID:
7466
Report Number(s):
ORNL/CP-102951; 64 70 62 00 1; ON: DE00007466
Country of Publication:
United States
Language:
English

Similar Records

Neutronics benchmarks of mixed-oxide fuels using the SCALE/CENTRM sequence
Technical Report · Mon Jan 31 23:00:00 EST 2000 · OSTI ID:752979
Comparison of the CENTRM resonance processor to the NITAWL resonance processor in SCALE
Journal Article · Tue Sep 01 00:00:00 EDT 1998 · Transactions of the American Nuclear Society · OSTI ID:644268
Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE
Conference · Sun Sep 17 00:00:00 EDT 1995 · OSTI ID:154860

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
Benchmarks
C Codes
Evaluated Nuclear Data File (ENDF)
Intermediate-Energy Spectrums
Iron
Monte Carlo N-Particle Transport (MCNP)
Multi-Level Briet-Wigner (MLBW)
Nordheim Integral Treatment
Nuclear Criticality Safety Program (NCSP)
Nuclear Data Collections
Reich-Moore (RM)
S Codes
Uranium