Conceptual design and thermal-hydraulic characteristics of natural circulation Boiling Water Reactors
- Energy Research Lab., Hitachi, Ltd., Moriyama-cho, Hitachi-shi 316 (JP)
- Hitachi Works, Hitachi Ltd., Saiwai-cho, Hitachi-shi 317 (JP)
A natural circulation boiling water reactor (BWR) with a rated capacity of 600 MW (electric) has been conceptually designed for small- and medium-sized light water reactors. The components and systems in the reactor are simplified by eliminating pumped recirculation systems and pumped emergency core cooling systems. Consequently, the volume of the reactor building is -- 50% of that for current BWRs with the same rated capacity; the construction period is also shorter. Its thermal-hydraulic characteristics, critical power ratio (CPR) and flow stability at steady state, decrease in the minimum CPR (..delta..MCPR) at transients, and the two-phase mixture level in the reactor pressure vessel (RPV) during accidents are investigated. The two-phase mixture level in the RPV during an accident does not decrease to lower than the top of the core; the core uncovery and heatup of fuel cladding would not occur during any loss-of-coolant accident.
- OSTI ID:
- 6564415
- Journal Information:
- Nucl. Technol.; (United States), Vol. 82:2
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
DESIGN
LOSS OF COOLANT
HYDRAULICS
PRESSURE VESSELS
TWO-PHASE FLOW
REACTOR ACCIDENTS
FUEL-CLADDING INTERACTIONS
REACTOR COOLING SYSTEMS
VOID FRACTION
ACCIDENTS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID FLOW
FLUID MECHANICS
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REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled