Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant /

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Bibliographic Details
Author / Creator:	Boyd, Christopher Fred.
Imprint:	Washington, DC : Safety Margins and Systems Analysis Branch, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 2000.
Description:	vii, 32 pages, 9 unnumbered pages : illustrations ; 28 cm
Language:	English
Subject:	Nuclear fuel elements -- Thermal properties. Spent reactor fuels -- Storage.
Format:	E-Resource U.S. Federal Government Document Book
URL for this record:	http://pi.lib.uchicago.edu/1001/cat/bib/6518999

Hidden Bibliographic Details
Other authors / contributors:	U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness. U.S. Nuclear Regulatory Commission. Safety Margins and Systems Analysis Branch.
ISBN:	0160592852
Notes:	"Date published: June 2000." "Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet. Includes bibliographical references. Technical. Available via Internet in PDF version and WordPerfect 6.1. 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.
Other form:	Boyd, Christopher Fred. Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant
GPO item no.:	1051-H-02 (online)
Govt.docs classification:	Y 3.N 88:10/1726

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