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
 

ENDF/B-V and ENDF/B-VI Results for UO2 Lattice Benchmark Problems Using MCNP

Conference ·
OSTI ID:314137
 [1]
  1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
+ Show Author Affiliations

Calculations for the ANS UO2 lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and ENDF/B-VI continuous-energy libraries. The ENDF/B-V library produces significantly better agreement with the benchmark value for keff than do the ENDF/B-VI libraries. However, the pin power distributions are essentially the same irrespective of the library.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
314137
Report Number(s):
LA-UR--98-2873; CONF-981003; ON: DE99001768
Country of Publication:
United States
Language:
English

Similar Records

ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP
Conference · Sat Aug 01 00:00:00 EDT 1998 · OSTI ID:674737
MCNP Calculations for Criticality Safety Benchmarks with ENDF/B-V and ENDF/B-VI Libraries
Conference · Sun Sep 17 00:00:00 EDT 1995 · OSTI ID:97187
Results of MCNP calculations for criticality safety benchmarks with ENDF/B-V and ENDF/B-VI libraries
Journal Article · Sat Dec 30 23:00:00 EST 1995 · Transactions of the American Nuclear Society · OSTI ID:186578

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
BENCHMARKS
Calculations
ENDF/B-V
ENDF/B-VI
EVALUATION
MCNP Monte Carlo Code
MULTIPLICATION FACTORS
NEUTRON SOURCES
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
POWER DISTRIBUTION
REACTOR LATTICES
RESEARCH REACTORS
URANIUM DIOXIDE