Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix II. Fault trees. [PWR and BWR]

Technical Report · Wed Oct 01 00:00:00 EDT 1975

DOI:https://doi.org/10.2172/7327159· OSTI ID:7327159

Information is presented concerning fault tree analysis;fault tree quantification; parametric studies of the effect of repair on long term failure probabilities; PWR fault trees; and BWR fault trees.

• Research Organization: Nuclear Regulatory Commission, Washington, D.C. (USA)
• OSTI ID: 7327159
• Report Number(s): WASH-1400(App.2); NUREG-75/014(App.2); TRN: 77-002140
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FAULT TREE ANALYSIS
REACTOR SAFETY
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
USA
REACTOR ACCIDENTS
ACCIDENTS
NORTH AMERICA
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled