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Title: Criticality Model Report

Abstract

The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's ability to accurately predict the effective neutron multiplication factor (k{sub eff}) for a range of conditions spanned by various critical configurations representative of the potential configurations commercial reactor assemblies stored in a waste package may take. Results of this work are an indication of the accuracy of MCNP for calculating eigenvalues, which will be used as input for criticality analyses for spent nuclear fuel (SNF) storage at the proposed Monitored Geologic Repository. The scope of this report is to document the development and validation of the criticality model. The scope of the criticality model is only applicable to commercial pressurized water reactor fuel. Valid ranges are established as part of the validation of the criticality model. This model activity follows the description in BSC (2002a).

Authors:
Publication Date:
Research Org.:
Office of Scientific and Technical Information, Oak Ridge, TN
Sponsoring Org.:
USDOE
OSTI Identifier:
859406
Report Number(s):
MDL-EBS-NU-GS-000003 REV 00 ICN 01
DOC.20030319.0001 DC#34795; TRN: US0600780
DOE Contract Number:
NA
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCURACY; CRITICALITY; EIGENVALUES; MULTIPLICATION FACTORS; NEUTRONS; NUCLEAR FUELS; PWR TYPE REACTORS; STORAGE; VALIDATION; WASTES

Citation Formats

J.M. Scaglione. Criticality Model Report. United States: N. p., 2003. Web. doi:10.2172/859406.
J.M. Scaglione. Criticality Model Report. United States. doi:10.2172/859406.
J.M. Scaglione. Wed . "Criticality Model Report". United States. doi:10.2172/859406. https://www.osti.gov/servlets/purl/859406.
@article{osti_859406,
title = {Criticality Model Report},
author = {J.M. Scaglione},
abstractNote = {The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's ability to accurately predict the effective neutron multiplication factor (k{sub eff}) for a range of conditions spanned by various critical configurations representative of the potential configurations commercial reactor assemblies stored in a waste package may take. Results of this work are an indication of the accuracy of MCNP for calculating eigenvalues, which will be used as input for criticality analyses for spent nuclear fuel (SNF) storage at the proposed Monitored Geologic Repository. The scope of this report is to document the development and validation of the criticality model. The scope of the criticality model is only applicable to commercial pressurized water reactor fuel. Valid ranges are established as part of the validation of the criticality model. This model activity follows the description in BSC (2002a).},
doi = {10.2172/859406},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Mar 12 00:00:00 EST 2003},
month = {Wed Mar 12 00:00:00 EST 2003}
}

Technical Report:

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