Improvement and verification of fast reactor safety analysis techniques

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An initial analysis of the KIWI-TNT experiment using the VENUS-II disassembly code has been completed. The calculated fission energy release agreed with the experimental value to within about 3 percent. An initial model for analyzing the SNAPTRAN-2 core disassembly experiment was also developed along with an appropriate equation-of-state. The first phase of the VENUS-II/PAD comparison study was completed through the issuing of a preliminary report describing the results. A new technique to calculate a P-V-work curve as a function of the degree of core expansion following a disassembly excursion has been developed. The technique provides results that are consistent with ... continued below

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Jackson, J.F. January 1, 1975.

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Description

An initial analysis of the KIWI-TNT experiment using the VENUS-II disassembly code has been completed. The calculated fission energy release agreed with the experimental value to within about 3 percent. An initial model for analyzing the SNAPTRAN-2 core disassembly experiment was also developed along with an appropriate equation-of-state. The first phase of the VENUS-II/PAD comparison study was completed through the issuing of a preliminary report describing the results. A new technique to calculate a P-V-work curve as a function of the degree of core expansion following a disassembly excursion has been developed. The technique provides results that are consistent with the ANL oxide-fuel equation-of-state in VENUS-II. Evaluation and check-out of this new model are currently in progress. (auth)

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  • Other Information: Orig. Receipt Date: 30-JUN-76

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  • Report No.: COO--2571-2
  • Grant Number: AT(11-1)-2571
  • DOI: 10.2172/4170232 | External Link
  • Office of Scientific & Technical Information Report Number: 4170232
  • Archival Resource Key: ark:/67531/metadc865447

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  • January 1, 1975

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Oct. 28, 2016, 4:27 p.m.

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Jackson, J.F. Improvement and verification of fast reactor safety analysis techniques, report, January 1, 1975; United States. (digital.library.unt.edu/ark:/67531/metadc865447/: accessed August 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.