METHOD FOR ANALYZING LOW-ENRICHMENT LIGHT-WATER CORES. SUPPLEMENTARY STUDY RELATED TO BONUS AND NUCLEAR SUPERHEAT PROGRAMS

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A three-group method is developed for analyzing lightwater UO/sub 2/ cores of low enrichment. The method is composed of a series of subroutines that are consolidated to produce a set of self-consistent multigroup parameters. The thermal cross sections are determined by averaging the cross section over a "hardened" or shifted Maxwellian spectrum, the amount of hardening being a function of the macroscopic absomption-to-slowing-down ratio. The disadvantage factor is calculated using diffusion theory for the moderator and a transport condition at the surface of the rod, the accuracy of the calculation being comparable to a g a shielding effects even for ... continued below

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Pages: 48

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Deutsch, R.W. October 1, 1960.

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Description

A three-group method is developed for analyzing lightwater UO/sub 2/ cores of low enrichment. The method is composed of a series of subroutines that are consolidated to produce a set of self-consistent multigroup parameters. The thermal cross sections are determined by averaging the cross section over a "hardened" or shifted Maxwellian spectrum, the amount of hardening being a function of the macroscopic absomption-to-slowing-down ratio. The disadvantage factor is calculated using diffusion theory for the moderator and a transport condition at the surface of the rod, the accuracy of the calculation being comparable to a g a shielding effects even for very close-packed lattices. The fast-fission factor is calculated relative to the experimental measurements for UO/sub 2/. The diffusion coefficients are found by averaging the measured cross sections over the appropriate neutron flux in each neutron energy group. The slowing-down cross section is defined as the diffusion coefficient divided by the neutron age, the age being determined by calculating equivalent transport and slowing-down factors relative to light-water measurements. Utilizing the two- dimensional IBM-704 PDQ digital computer code, a comparison is made with the available experimental information using oxide fuel. These experiments, which include rod-type fuel elements, use U/sup 235/ enrichments from 1.3 to 4.0 wt.% and water-to-uranium-metal ratios from 2.2 to 4.9. The reactivity and power- distribution predictions are very good: The reactivity calculations check to within 2% delta k for all cases, most cases being with 1% delta k. (auth)

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Pages: 48

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  • Other Information: Orig. Receipt Date: 31-DEC-61

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  • Report No.: GNEC-133
  • Grant Number: AT(40-1)-2674
  • DOI: 10.2172/4147208 | External Link
  • Office of Scientific & Technical Information Report Number: 4147208
  • Archival Resource Key: ark:/67531/metadc872598

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  • October 1, 1960

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  • Sept. 16, 2016, 12:32 a.m.

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  • Nov. 29, 2016, 8:03 p.m.

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Deutsch, R.W. METHOD FOR ANALYZING LOW-ENRICHMENT LIGHT-WATER CORES. SUPPLEMENTARY STUDY RELATED TO BONUS AND NUCLEAR SUPERHEAT PROGRAMS, report, October 1, 1960; United States. (digital.library.unt.edu/ark:/67531/metadc872598/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.