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Title: Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks

Abstract

A probability-table treatment recently has been incorporated into an intermediate version of the MCNP Monte Carlo code named MCNP4XS. This paper presents MCNP4XS results for a variety of uranium and plutonium criticality benchmarks, calculated with and without the probability-table treatment. It is shown that the probability-table treatment can produce small but significant reactivity changes for plutonium and {sup 233}U systems with intermediate spectra. More importantly, it can produce substantial reactivity increases for systems with large amounts of {sup 238}U and intermediate spectra.

Authors:
;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
761232
Report Number(s):
LA-UR-99-2300
TRN: US0100591
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Sixth International Conference on Nuclear Criticality Safety (ICNC '99), Versailles (FR), 09/20/1999--09/24/1999; Other Information: PBD: 20 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BENCHMARKS; CRITICALITY; PLUTONIUM; RESONANCE; SAFETY; SPECTRA; URANIUM

Citation Formats

Mosteller, R.D., and Little, R.C. Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks. United States: N. p., 1999. Web.
Mosteller, R.D., & Little, R.C. Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks. United States.
Mosteller, R.D., and Little, R.C. Mon . "Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks". United States. https://www.osti.gov/servlets/purl/761232.
@article{osti_761232,
title = {Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks},
author = {Mosteller, R.D. and Little, R.C.},
abstractNote = {A probability-table treatment recently has been incorporated into an intermediate version of the MCNP Monte Carlo code named MCNP4XS. This paper presents MCNP4XS results for a variety of uranium and plutonium criticality benchmarks, calculated with and without the probability-table treatment. It is shown that the probability-table treatment can produce small but significant reactivity changes for plutonium and {sup 233}U systems with intermediate spectra. More importantly, it can produce substantial reactivity increases for systems with large amounts of {sup 238}U and intermediate spectra.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}

Conference:
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