Uncertainties in TRAC plenum pressures for the FI phase of a DEGB LOCA

Uncertainties in TRAC plenum pressures for the FI phase of a DEGB LOCA [electronic resource]

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The TRAC-PF1/MOD1 code (TRAC) is used to perform best-estimate analyses of certain postulated Design Basis Accidents (DBAs) in SRS production reactors. Currently, the most limiting DBA in terms of reactor power level is an instantaneous double-ended guillotine break (DEGB) loss of coolant accident (...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Westinghouse Savannah River Company (Researcher), United States. Department of Energy. Savannah River Site (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Defense ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1991.
Subjects:
Safety.
Special Production Reactors.
Hydraulics.
Us Doe.
Savannah River Plant.
Limiting Values.
Reactor Safety.
Fluid Flow.
National Organizations.
Production Reactors.
Energy Transfer.
Mechanics.
F Codes.
Heavy Water Moderated Reactors.
Computer Codes.
L Reactor.
Fluid Mechanics.
Reactor Accidents.
Us Aec.
Design Basis Accidents.
Us Organizations.
Cooling Systems.
Reactors.
Data Covariances.
R Codes.
Heat Transfer.
T Codes.
Us Erda.
Loss Of Coolant.
Reactor Components.
Stability.
Reactor Cooling Systems.
Accidents.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:wsrc-tr-90-263
E 1.99:wsrc-tr-90-263 Available

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