Evaluation of thermal response in Fort St. Vrain reactor primary system to a design basis depressurization accident followed by cooling with two Pelton wheel drives operating at 7000 rpm

Evaluation of thermal response in Fort St. Vrain reactor primary system to a design basis depressurization accident followed by cooling with two Pelton wheel drives operating at 7000 rpm [electronic resource]

Independent computations have been performed at ORNL to determine the thermal and hydraulic response of the primary system of the Fort St. Vrain reactor to a specified design basis depressurization accident (DBDA). For this accident it is stated that two of the four auxiliary drives on the circulato...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1975.
Subjects:
*Vrain Reactor > Design Basis Accidents.
Comparative Evaluations.
Computer Codes.
Heat Transfer.
Hydraulics.
Primary Coolant Circuits.
Reactor Safety.
Steam Systems.
Temperature Distribution.
Temperature Gradients.
N77900* > Reactors > Reactor Safety & Environmental Aspects.
N77300 > Reactors > Power Reactors, Non-Breeding, Graphite Moderated.
0900* > Nuclear Reactor Technology > Reactor Safety.

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Call Number: E 1.99:ornl-tm--5140
E 1.99:ornl-tm--5140 Available

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