Predictions of spent fuel heatup after a complete loss of spent fuel pool coolant
By: prepared by Christopher F. Boyd.
Contributors: U.S. Nuclear Regulatory Commission. Safety Margins and Systems Analysis Branch.; U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness.
Publisher: Safety Margins and Systems Analysis Branch, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 2000
Place of publication: Washington, DC
Language: eng
Number of pages: 32
Subjects: Spent reactor fuels -- Storage.; Nuclear fuel elements -- Thermal properties.
Notes: "Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.

"Date published: June 2000."

Includes bibliographical references.

Technical.

Available via Internet from the NUREG 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.