Posttest analysis of international standard problem 10 using RELAP4/MOD7. [PWR]

Posttest analysis of international standard problem 10 using RELAP4/MOD7. [PWR] [electronic resource]

RELAP4/MOD7, a best estimate computer code for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This paper evaluates the capability of RELAP4/MOD7 to calculate refill/reflood phenomena. This evalua...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: EG & G Idaho (Researcher), Idaho National Engineering Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Idaho Falls, Idaho : Oak Ridge, Tenn. : Idaho National Engineering Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1981.
Subjects:
Safety.
Hydraulics.
Computer Calculations.
Temperature Distribution.
Water Moderated Reactors.
Water Cooled Reactors.
Reactors.
Reactor Safety.
Heat Transfer.
Energy Transfer.
Mechanics.
Loss Of Coolant.
Pwr Type Reactors.
Accidents.
Fluid Mechanics.
Reactor Accidents.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-810606-73
E 1.99:conf-810606-73 Available

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