Impact of MCNP unresolved resonance probability-table treatment on {sup 233}U benchmarks

Conference · Tue Jun 01 00:00:00 EDT 1999

OSTI ID:350950

Mosteller, R D

Previous versions of the MCNP Monte Carlo code, up through and including MCNP4B, have not accurately modeled neutron self-shielding effects in the unresolved resonance energy region. Recently, a probability-table treatment has been incorporated into an intermediate version called MCNP4XS, and compatible continuous-energy cross-section libraries have been developed for 27 different isotopes. Preliminary results for a variety of uranium and plutonium benchmarks have been presented previously, and this paper extends those results to include several {sup 233}U benchmarks. The objective of the current study is to assess the reactivity impact of the probability-table treatment on {sup 233}U systems.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE Assistant Secretary for Management and Administration, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 350950
• Report Number(s): LA-UR-99-152; CONF-990605-; ON: DE99002733; TRN: AHC29921%%136
• Resource Relation: Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: [1999]
• Country of Publication: United States
• Language: English

Related Subjects

99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
22 NUCLEAR REACTOR TECHNOLOGY
M CODES
SELF-SHIELDING
PROBABILITY
URANIUM 233
BENCHMARKS
RESONANCE NEUTRONS
CROSS SECTIONS
REACTIVITY
LIBRARIES
ZERO POWER REACTORS