Identification and evaluation of PWR in-vessel severe accident management strategies
Identification and evaluation of PWR in-vessel severe accident management strategies
This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.
- Pacific Northwest National Laboratory United States
- University of North Texas System United States
Enriched Uranium Reactors, Reactor Safety, 22 General Studies Of Nuclear Reactors, Emergency Plans, Nonbreeding, Nonboiling Water Cooled, Pwr Type Reactors, Thermal Reactors, 21 Specific Nuclear Reactors And Associated Plants, Reactors, Risk Assessment, Reactor Accidents, Containers, Management, Reactor Vessels, Power Reactors, Accidents, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Light-Water Moderated
Enriched Uranium Reactors, Reactor Safety, 22 General Studies Of Nuclear Reactors, Emergency Plans, Nonbreeding, Nonboiling Water Cooled, Pwr Type Reactors, Thermal Reactors, 21 Specific Nuclear Reactors And Associated Plants, Reactors, Risk Assessment, Reactor Accidents, Containers, Management, Reactor Vessels, Power Reactors, Accidents, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Light-Water Moderated
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