NRC Perspectives on Reactor Safety Course Special Features of BWR Severe Accident Mitigation and Progression. Appendix 2B-7 Module 3 Section 7 Module 4 Section 7. L. J. Ott Oak Ridge National Laboratory. BWR Severe Accident Studies Were Conducted at Oak Ridge National Laboratory 1980-1999.
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NRC Perspectives on Reactor Safety CourseSpecial Features of BWR Severe Accident Mitigation and Progression
Module 3 Section 7
Module 4 Section 7
L. J. Ott
Oak Ridge National Laboratory
Immediate Loss ofWater Makeup
Loss of Water Makeup Following Battery Exhaustion
Station Blackout Core
*From Plant IPE (NPE 86-003)
Grand GulfShort TermStation Blackout without ADS Actuation
The BWR Control Rod Drive Mechanism Assemblies Are Held in Place by Upper Stub Tube Welds; the Incore Instrument Tubes Are Supported by Welds at the Vessel Wall