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.

Bibliographic Details
Main Author:	Ortiz, M. G.
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research Idaho National Engineering Laboratory EG & G Idaho
Other Authors:	Ghan, L. S.
Language:	English
Published:	Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
Subjects:	Pressurized water reactors > Loss of coolant > Computer simulation. Nuclear reactors > Cooling > Computer simulation.
Physical Description:	1 volume (various pagings) : illustrations ; 28 cm
Format:	Government Document Microfilm Book

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