BWR reactor vessel bottom head failure modes
Boiling water reactors (BWRs) incorporate many unique structural features that make their expected response under severe accident conditions very different from that predicted in the case of pressurized water reactor accident sequences. The effect of the BWR procedural and structural differences upon the progression of a severe accident sequence during the period preceding movement of core debris into the reactor vessel lower plenum has been discussed previously. It is the purpose of this paper to briefly address the events occurring after debris relocation past the core plate and to describe the subsequent expected modes of bottom head pressure boundary failure. As an example, the calculated timing of events for the unmitigated short-term station blackout severe accident sequence at the Peach Bottom Atomic Power Station is also presented. 14 refs., 4 figs., 1 tab.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6124656
- Report Number(s):
- CONF-890546-3; ON: DE89009623; TRN: 89-011253
- Resource Relation:
- Conference: Seminar on fission product transport processes in reactor accidents, Dubrovnik, Yugoslavia, 22 May 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermalhydraulic processes in the reactor coolant system of a BWR (boiling water reactor) under severe accident conditions
An Overview of the State-of-the-Art Reactor Consequence Uncertainty Assessment Accident Progression Insights
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PEACH BOTTOM-2 REACTOR
REACTOR CORE DISRUPTION
PEACH BOTTOM-3 REACTOR
CORIUM
CREEP
HEAT TRANSFER
HYDRAULICS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
RUPTURES
STANDARDS
TUBES
ACCIDENTS
BWR TYPE REACTORS
CONTAINERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
MECHANICAL PROPERTIES
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled