An analysis of a feed-and-bleed mode of PWR emergency core cooling
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5094589
None
- Research Organization:
- Rensselaer Polytechnic Institute, Troy, NY 12181
- OSTI ID:
- 5094589
- Report Number(s):
- CONF-831047-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
CONTROL EQUIPMENT
COOLING SYSTEMS
DESIGN
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FLOW REGULATORS
HEAT TRANSFER
HPCI
LOSS OF COOLANT
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
RELIEF VALVES
STEAM GENERATORS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
CONTROL EQUIPMENT
COOLING SYSTEMS
DESIGN
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FLOW REGULATORS
HEAT TRANSFER
HPCI
LOSS OF COOLANT
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
RELIEF VALVES
STEAM GENERATORS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS