Published June 1997
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Calculation of K∞ for homogeneous 235U metal mixtures: Will the real K∞ please stand up?
- 1. Oak Ridge National Lab., TN (United States)
Description
This paper very briefly analyzes a journal article about calculating k∞ for metals mixed with uranium 235, and compares the article results with other calculation methods. The article suggested that continuous energy cross sections gave more accurate results than groupwise cross sections. The mixtures described in the article were dry, fast systems with several unusual characteristics; however, the majority of multigroup libraries used for analysis were developed for well moderated thermal systems. The results of calculations performed using several different codes and cross sections for three uranium/metal mixtures are presented in this paper. 1 tab
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the nuclear criticality technology safety project
- Imprint Pagination
- 184 p.
- Journal Page Range
- p. 29-31.
- Report number
- LA--13277-C
Conference
- Title
- Nuclear criticality technology safety project workshop.
- Dates
- 10-11 May 1994.
- Place
- Williamsburg, VA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29022189
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; CALCULATION METHODS; CRITICALITY; IRON; METALS; REACTOR SAFETY; URANIUM 235; ZIRCONIUM
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; ELEMENTS; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIOISOTOPES; SAFETY; SPONTANEOUS FISSION RADIOISOTOPES; TRANSITION ELEMENTS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-9405144--.