Impact of MCNP unresolved resonance probability-table treatment on {sup 233}U benchmarks
Conference
·
OSTI ID:350950
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
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Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks
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Conference
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Mon Sep 20 00:00:00 EDT 1999
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OSTI ID:350950
Impact of MCNP unresolved resonance probability-table treatment on uranium and plutonium benchmarks
Journal Article
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Thu Dec 31 00:00:00 EST 1998
· Transactions of the American Nuclear Society
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OSTI ID:350950
Impact of MCNP unresolved resonance probability-table treatment on uranium and plutonium benchmarks
Conference
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Thu Dec 31 00:00:00 EST 1998
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OSTI ID:350950