Nuclide importance to criticality safety, decay heating, and source terms related to transport and interim storage of high-burnup LWR fuel
By: prepared by I.C. Gauld, J.C. Ryman.
Contributors: Ryman, J. C.; U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness.; Oak Ridge National Laboratory.
Publisher: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 2001
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 84
Subjects: Spent reactor fuels -- Transportation.; Spent reactor fuels -- Storage.; Light water reactors.; Nuclides.
Notes: "Oak Ridge National Laboratory."

Shipping list no.: 2001-0255-M.

"Date published: January 2001."

"NUREG/CR-6700."

"ORNL/TM-2000/284."

Includes bibliographical references (p. 59-60).

Technical.

Also available via Internet from the NRC web site (PDF only). Address as of 5/18/01: http://www.nrc.gov/NRC/NUREGS/CR6700/cr6700.pdf; current access is available via PURL.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2001] 2 microfiches : negative. Microfiche reproduction lacks p. xii, which is blank.

W6479.