Contribution of Anticipated Transients Without Scram (ATWS) to core melt at United States nuclear power plants

Technical Report · Fri Sep 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/6892419· OSTI ID:6892419

Giachetti, R T ^[1]

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1. Giachetti (Richard T.), Ann Arbor, MI (USA)

This report looks at WASH-1400 and several other Probabilistic Risk Assessments (PRAs) and Probabilistic Safety Studies (PSSs) to determine the contribution of Anticipated Transients Without Scram (ATWS) events to the total core melt probability at eight nuclear power plants in the United States. After considering each plant individually, the results are compared from plant to plant to see if any generic conclusions regarding ATWS, or core melt in general, can be made. 8 refs., 34 tabs.

• Research Organization: Oak Ridge Associated Univ., Oak Ridge, TN (United States)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC05-76OR00033
• OSTI ID: 6892419
• Report Number(s): DOE/OR/00033-T442; ON: DE90017508; TRN: 90-029480
• 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
ATWS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
BIG ROCK POINT REACTOR
COMPILED DATA
FLOODS
HISTORICAL ASPECTS
INDIAN POINT-2 REACTOR
INDIAN POINT-3 REACTOR
LIMERICK-1 REACTOR
LOSS OF COOLANT
MELTDOWN
OCONEE-3 REACTOR
PEACH BOTTOM-2 REACTOR
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
SURRY-1 REACTOR
TORNADOES
TRANSIENTS
USA
ZION-1 REACTOR
ACCIDENTS
DATA
DISASTERS
ENRICHED URANIUM REACTORS
INFORMATION
NORTH AMERICA
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
STORMS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WIND
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