Normal görünüm MARC görünümü ISBD görünümü

Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B&W plant an application of the CSAU methodology using the RELAP5 MOD3 computer code prepared by M.G. Ortiz, L.S. Ghan. - Washington DC Division of Systems Research Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission : 1992 - 1 v. (various pagings), ill. 28 cm.

"Date published: December 1992." "EG & G Idaho, Inc." "EGG-2665." "Idaho National Engineering Laboratory." "NUREG/CR-5818." Distributed to depository libraries in microfiche. Shipping list no.: 93-0363-M.

Includes bibliographical references.

Technical.

Subjects--Topical Terms:
Nuclear reactors--Computer simulation.
Pressurized water reactors--Loss of coolant

Dewey Class. No.: 621.4834 UNC 1992

GPO Item No.: 1051-H-11 (MF)

Gov. Doc. Class. No.: Y 3.N 88:25/5818