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Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant / prepared by Christopher F. Boyd.

Boyd, Christopher Fred.(Author).
U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness.(Added Author).

Available copies

  • 2 of 2 copies available at Evergreen Indiana.

Current holds

0 current holds with 2 total copies.

Show Only Available Copies
Location Call Number / Copy Notes Barcode Shelving Location Status Due Date
Indiana State Library - Indianapolis Y 3.N 88:10/1726 (Text) 716319-1001 General Federal documents Available -
Indiana State Library - Indianapolis Y 3.N 88:10/1726 (Text) 716319-1002 Online document Available -

Record details

  • ISBN: 0160592852
  • Physical Description: vii, 32 pages, 5 pages, 4 pages : illustrations ; 28 cm
  • Publisher: Washington, DC : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission : 2000.

Content descriptions

General Note:
Shipping list no.: 2001-0110-M.
"Date published: June 2000."
"NUREG 1726."
Bibliography, etc. Note:
Includes bibliographical references.
Type of Report and Period Covered Note:
Technical.
Additional Physical Form available Note:
Also available via Internet from the NRC web site. Address as of 10/10/00: http://www.nrc.gov/NRC/NUREGS/SR1726/sr1726.html; current access is available via PURL.
Also available via Internet in PDF version and WordPerfect 6.1.
Reproduction Note:
Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2000] 1 microfiche : negative.

Search for related items by subject

Subject: Spent reactor fuels > Storage.
Nuclear fuel elements > Thermal properties.

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