Quantifying reactor safety margins
Subtitle: application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident
By: prepared by technical program group, B. Boyack ... [et al.] ; contributing authors, K.R. Katsma ... [et al.].
Contributors: Boyack, B. E.; Katsma, K. R.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research.; Idaho National Engineering Laboratory.; EG & G Idaho.
Publisher: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1989
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 239
Subjects: Water cooled reactors -- Loss of coolant -- Computer simulation.; Light water reactors -- Accidents -- Computer simulation.; Light water reactors -- Safety measures.
Notes: "Idaho National Engineering Laboratory."

"EG&G Idaho, Inc."

Distributed to depository libraries in microfiche.

Shipping list no.: 92-1198-M.

Paper version no longer for sale by the Supt. of Docs.

"Date published: December 1989."

"NUREG/CR-5249."

"EGG-2552."

"Prepared ... under DOE contract no. DE-AC07-76ID01570."

Includes bibliographical references.

Research.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1992] 5 microfiches : negative.

A6868.