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Author Parks, C. V. ♦ Jordan, W. C. ♦ Petrie, L. M. ♦ Wright, R. Q.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword ENGINEERING NOT INCLUDED IN OTHER CATEGORIES ♦ MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS ♦ CRITICALITY ♦ M CODES ♦ URANIUM 235 ♦ MIXTURES ♦ CROSS SECTIONS ♦ IRON
Abstract A table of k. values for three homogenized metal/{sup 235}U systems calculated using both MCNP and the SCALE code system was presented. The homogenized metal/{sup 211}U ratios were selected such that the MCNP analyses for each mixture provided k{sub {infinity}} {congruent} 1.0. The metals considered were aluminum, zirconium, and iron. These simplified systems were created in an effort to ease an investigation of discrepant results obtained using MCNP and SCALE to analyze large, dry systems of metal-clad, highly enriched fuel assemblies. The simplified systems are all dominated by scattering and fission in the intermediate energy range of 10 eV to 1 MeV and, as such, provide a severe test of the cross-section data and processing methodologies in this energy range. Unfortunately, no exponents adequately represent the characteristics of these metal/{sup 235}U systems, thus the ability of the codes to predict the {open_quotes}correct{close_quotes} critical metal/{sup 235}U ratios is not known. In the absence of experimental data, states that the continuous-energy cross sections, in combination with MCNP, are {open_quotes}most likely to give the correct results.{close_quotes} The results in this paper, however, illustrate the potential dangers embedded in drawing such a conclusion in the absence of applicable experimental data.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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