Interim reliability evaluation program, Browns Ferry 1

Interim reliability evaluation program, Browns Ferry 1 [electronic resource]

Probabilistic risk analysis techniques, i.e., event tree and fault tree analysis, were utilized to provide a risk assessment of the Browns Ferry Nuclear Plant Unit 1. Browns Ferry 1 is a General Electric boiling water reactor of the BWR 4 product line with a Mark 1 (drywell and torus) containment. W...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: EG & G Idaho (Researcher), Idaho National Engineering and Environmental Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Idaho Falls, Idaho : Oak Ridge, Tenn. : Idaho National Engineering and Environmental Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1981.
Subjects:
Safety.
Water Moderated Reactors.
Browns Ferry-1 Reactor.
Systems Analysis.
Water Cooled Reactors.
Bwr Type Reactors.
Reactors.
Reactor Safety.
Enriched Uranium Reactors.
Reliability.
Risk Assessment.
Power Reactors.
Failures.
System Failure Analysis.
Fault Tree Analysis.
Mixed Spectrum Reactors.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99: conf-810905-29
E 1.99: conf-810905-29 Available

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