Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B&W plant
Subtitle: an application of the CSAU methodology using the RELAP5/MOD3 computer code
By: prepared by M.G. Ortiz, L.S. Ghan.
Contributors: Ghan, L. S.; 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; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 1992
Place of publication: Washington, DC
Language: eng
Format: Microform
Subjects: Pressurized water reactors -- Loss of coolant -- Computer simulation.; Nuclear reactors -- Cooling -- Computer simulation.
Notes: "Idaho National Engineering Laboratory."

"EG & G Idaho, Inc."

Distributed to depository libraries in microfiche.

Shipping list no.: 93-0363-M.

"Date published: December 1992."

"NUREG/CR-5818."

"EGG-2665."

Includes bibliographical references.

Technical.

Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1993] 2 microfiche : negative.

L1111.