Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix V. Quantitative results of accident sequences. [PWR and BWR]

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

DOI:https://doi.org/10.2172/7327158· OSTI ID:7327158

The methods used to quantify the accident sequences previously defined in Appendix I that can potentially lead to the release of significant amounts of radioactivity from nuclear power plants are presented. The objective of this quantification was to provide the input information needed to perform calculations of the consequences of these accident sequences as described in Appendix VI.

• Research Organization: Nuclear Regulatory Commission, Washington, D.C. (USA)
• OSTI ID: 7327158
• Report Number(s): WASH-1400(App.5); NUREG-75/014(App.5); TRN: 77-002142
• 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
REACTOR ACCIDENTS
REACTOR SAFETY
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
ENVIRONMENTAL EFFECTS
FISSION PRODUCT RELEASE
USA
RADIATION HAZARDS
ACCIDENTS
HAZARDS
HEALTH HAZARDS
NORTH AMERICA
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
SAFETY
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