Identification and initial assessment of candidate BWR late-phase in-vessel accident management strategies [electronic resource].
- Published:
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1991.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: (32 pages) : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Work sponsored by the United States Nuclear Regulatory Commission (USNRC) to identify and perform preliminary assessments of candidate BWR (boiling water reactor) in-vessel accident management strategies was completed at Oak Ridge National Laboratory (ORNL) during fiscal year 1990. Mitigative strategies for containment events have been the subject of a companion study at Brookhaven National Laboratory. The focus of this Oak Ridge effort was the development of new strategies for mitigation of the late phase events, that is, the events that would occur in-vessel after the onset of significant core damage. The work began with an investigation of the current status of BWR in-vessel accident management procedures and proceeded through a preliminary evaluation of several candidate new strategies. The steps leading to the identification of the candidate strategies are described. The four new candidate late-phase (in-vessel) accident mitigation strategies identified by this study and discussed in the report are: (1) keep the reactor vessel depressurized; (2) restore injection in a controlled manner; (3) inject boron if control blade damage has occurred; and (4) containment flooding to maintain core and structural debris in-vessel. Additional assessments of these strategies are proposed.
- Report Numbers:
- E 1.99:conf-9104223-1
conf-9104223-1 - Subject(s):
- Other Subject(s):
- Bwr Type Reactors
- Reactor Core Disruption
- Emergency Plans
- Ac Systems
- After-Heat Removal
- Atws
- Blackouts
- Containment Systems
- Control Elements
- Core Flooding Systems
- Corium
- Decision Making
- Depressurization
- Diesel Engines
- Eccs
- Electric Generators
- Loss Of Coolant
- Meltdown
- Mitigation
- Ornl
- Pressure Control
- Pressure Vessels
- Primary Coolant Circuits
- Reactivity
- Reactor Accidents
- Reactor Operators
- Reactor Safety
- Reliability
- Risk Assessment
- Safety Injection
- Temperature Control
- Us Nrc
- Accidents
- Containers
- Containment
- Control
- Cooling Systems
- Energy Systems
- Engineered Safety Systems
- Engines
- Heat Engines
- Internal Combustion Engines
- National Organizations
- Personnel
- Power Systems
- Reactor Components
- Reactor Cooling Systems
- Reactor Protection Systems
- Reactors
- Removal
- Safety
- Us Aec
- Us Doe
- Us Erda
- Us Organizations
- Water Cooled Reactors
- Water Moderated Reactors
- Note:
- Published through SciTech Connect.
04/15/1991.
"conf-9104223-1"
"DE91010997"
United States Nuclear Regulatory Commission (USNRC) BMU/GRS (Society for Reactor Safety) accident management information exchange meeting, Rockville, MD (USA), 15 Apr 1991.
Hodge, S.A. - Funding Information:
- AC05-84OR21400
View MARC record | catkey: 14370844