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]

Show other versions (1)

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 (...

Full description

Saved in:
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 Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1991.
Subjects:
Design Basis Accidents.
Hydraulics.
Savannah River Plant.
Reactor Safety.
Limiting Values.
Fluid Flow.
Data Covariances.
R Codes.
Production Reactors.
Heat Transfer.
F Codes.
T Codes.
Loss Of Coolant.
Stability.
Reactor Cooling Systems.
L Reactor.
General Studies Of Nuclear Reactors.

Internet

Online Access

Online

Holdings details from Online
Call Number: E 1.99:wsrc-tr--90-263
E 1.99:wsrc-tr--90-263 Available

Similar Items