Correlation for predicting reactor power during a BWR ATWS
An anticipated transient without scram (ATWS), while of low probability, has received much attention because of its potentially serious consequences. Under certain ATWS sequences for a boiling water reactor (BWR), it would be desirable to reduce system power, particularly where the primary system has been isolated by closure of all main steam isolation valves and is discharging steam through its safety/relief valve system to the suppression pool. Reducing reactor power increases the time available to shut down the reactor by minimizing the heat dumped to the suppression pool and thereby helping to keep the suppression pool temperature and the containment stresses with limits. This paper describes the correlation developed to provide the degree of power reduction which can be achieved for a BWR during ATWS conditions by intentionally reducing the system coolant inventory and pressure. Under proposed emergency procedure guidelines for the ATWS event, the reactor water level would be lowered to reduce system power. The correlation is based on three-dimensional quasi-static analysis based on Electric Power Research Institute computer codes NATBWR and verified by the transient code RETRAN-02.
- Research Organization:
- EPRI, Palo Alto, CA
- OSTI ID:
- 6992950
- Report Number(s):
- CONF-861102-; TRN: 87-008125
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
BWR TYPE REACTORS
REACTOR SAFETY
COMPUTER CODES
COMPUTERIZED SIMULATION
EMERGENCY PLANS
EPRI
N CODES
POWER DISTRIBUTION
PRIMARY COOLANT CIRCUITS
PROBABILITY
REACTOR KINETICS
REACTOR SHUTDOWN
RELIEF VALVES
ACCIDENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
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FLUID MECHANICS
KINETICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SHUTDOWNS
SIMULATION
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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