Primary coolant feed and bleed operating regions for the Midland Plant
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5053571
Operating regions for primary coolant feed and bleed cooling are developed for the Midland Plant using core decay heat, the high-pressure injection (HPI) system capacity, and flow rate relief through the power-operated relief valve (PORV). This mode of cooling is used for accident scenarios in which the normal core cooling means of a nuclear power plant is lost because of loss of water inventory in the steam generators. The HPI flow is based on the capacities of one and two pumps. Saturated steam, saturated water, and subcooled water are considered to be possible states of the fluid being relieved through the PORV. In estimating the PORV relief rate, flow equations are derived from the Electric Power Research Institute test data obtained from the same model and size valve that is used in the Midland Plant. For easy reference by operators, the operating region is displayed on a plane of reactor coolant system pressure and temperature. The technique developed for the Midland Plant provides a convenient method for examining the feed and bleed cooling capability for a nuclear power plant that employs a pressurized water reactor system.
- Research Organization:
- Consumers Power Company, Jackson, Michigan
- OSTI ID:
- 5053571
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 68:3; ISSN NUTYB
- 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
AFTER-HEAT REMOVAL
CONTROL EQUIPMENT
CONTROL SYSTEMS
COOLING
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPRI
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
MIDLAND-1 REACTOR
MIDLAND-2 REACTOR
POWER REACTORS
PROCESS HEAT REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIEF VALVES
REMOVAL
SAFETY
VALVES
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
AFTER-HEAT REMOVAL
CONTROL EQUIPMENT
CONTROL SYSTEMS
COOLING
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPRI
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
MIDLAND-1 REACTOR
MIDLAND-2 REACTOR
POWER REACTORS
PROCESS HEAT REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIEF VALVES
REMOVAL
SAFETY
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS