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TRAC-PF1 MOD1 post test calculations of the OECD LOFT Experiment LP-SB-1 [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Main Author:	Allen, E J (Author)
Corporate Author:	U.S. Nuclear Regulatory Commission (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Rockville, Md. : Oak Ridge, Tenn. : U.S. Nuclear Regulatory Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1990.
Subjects:	Loft Reactor. Loss Of Coolant. Boundary Conditions. Computer Calculations. Flow Rate. Heat Transfer. Hydraulics. Reactor Cooling Systems. Reactor Safety. Steady-State Conditions. T Codes. Test Facilities. Accidents. Computer Codes. Cooling Systems. Energy Systems. Energy Transfer. Fluid Mechanics. Mechanics. Pwr Type Reactors. Reactor Accidents. Reactor Components. Reactors. Research And Test Reactors. Safety. Tank Type Reactors. Test Reactors. Water Cooled Reactors. Water Moderated Reactors. General Studies Of Nuclear Reactors. Specific Nuclear Reactors And Associated Plants.

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Call Number:	E 1.99:nureg/ia-0011
E 1.99:nureg/ia-0011	Available