Review of Heat Transfer Models in GOTH_SNF for Spent Fuel MCO Calculations

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Description

The present report is one of a series of three. The series provides an independent technical review of certain aspects of the GOTH-SNF code that is used for accident analysis of the multicanister overpack that is proposed for permanent storage of spent nuclear fuel in the planned repository at Yucca Mountain, Nevada. The work documented in the present report and its two companions was done under the auspices of the National Spent Nuclear Fuel Program. The other two reports in the series are DOE/SNF/REP-0871 and DOE/SNF/REP-089.2

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Kirkpatrick, John R. & Dahl, Chris A. September 1, 2003.

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Description

The present report is one of a series of three. The series provides an independent technical review of certain aspects of the GOTH-SNF code that is used for accident analysis of the multicanister overpack that is proposed for permanent storage of spent nuclear fuel in the planned repository at Yucca Mountain, Nevada. The work documented in the present report and its two companions was done under the auspices of the National Spent Nuclear Fuel Program. The other two reports in the series are DOE/SNF/REP-0871 and DOE/SNF/REP-089.2

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  • Report No.: DOE/SNF/REP-088
  • Grant Number: DE-AC07-99ID-13727
  • DOI: 10.2172/911529 | External Link
  • Office of Scientific & Technical Information Report Number: 911529
  • Archival Resource Key: ark:/67531/metadc887657

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  • September 1, 2003

Added to The UNT Digital Library

  • Sept. 22, 2016, 2:13 a.m.

Description Last Updated

  • Nov. 7, 2016, 8 p.m.

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Kirkpatrick, John R. & Dahl, Chris A. Review of Heat Transfer Models in GOTH_SNF for Spent Fuel MCO Calculations, report, September 1, 2003; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc887657/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.