Modeling the behavior of metallic fast reactor fuels during extended transients

Modeling the behavior of metallic fast reactor fuels during extended transients [electronic resource]

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Passive safety features in the metal-fueled Integral Fast Reactor (IFR) make it possible to avoid core damage for extended time periods even when automatic scram systems fail to operate or heat removal systems are severely degraded. The time scale for these transients are intermediate between those...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (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, 1992.
Subjects:
Ifr Reactor.
Heat Transfer.
Reactor Cores.
Nuclear Fuels.
Transients.
Reactor Safety.
Performance.
Reactor Core Disruption.
Transient Overpower Accidents.
Damage.
Loss Of Flow.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99: conf-921102--30
E 1.99: conf-921102--30 Available

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