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

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Published 1992 by Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC .
Written in English

Subjects:

• Pressurized water reactors -- Loss of coolant -- Computer simulation.,
• Nuclear reactors -- Cooling -- Computer simulation.

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Edition Notes

Statement	prepared by M.G. Ortiz, L.S. Ghan.
Contributions	Ghan, L. S., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory., EG & G Idaho.
The Physical Object
Format	Microform
Pagination	1 v. (various pagings)
ID Numbers
Open Library	OL14691986M

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