RELAP4/MOD6 assessment

RELAP4/MOD6 assessment [electronic resource]

The use of RELAP4/MOD6 computer program for analyzing loss-of-coolant accident conditions in PWR type reactors is described.

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Bibliographic Details
Online Access:	Online Access
Main Author:	Charlton, T.R (Author)
Corporate Author:	Idaho National Engineering Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1979.
Subjects:	Loss Of Coolant. Heat Transfer. Hydraulics. Pwr Type Reactors. Computer Calculations. Reactor Safety. Temperature Gradients. Accidents. Fluid Mechanics. Mechanics. Reactor Accidents. Reactors. Comparative Evaluations. Safety. Water Cooled Reactors. Energy Transfer. Water Moderated Reactors. General Studies Of Nuclear Reactors. Specific Nuclear Reactors And Associated Plants.

Description
Summary:	The use of RELAP4/MOD6 computer program for analyzing loss-of-coolant accident conditions in PWR type reactors is described.
Item Description:	Published through SciTech Connect. 01/01/1979. "conf-791123-2" Water reactor safety meeting, Washington, DC, USA, 5 Nov 1979. Charlton, T.R. Idaho National Engineering Lab., Idaho Falls (USA)
Physical Description:	Pages: 20 : digital, PDF file.