Palo Verde Nuclear Generating Station midloop condition retran model
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:5080925
- Arizona Public Service Co., Phoenix, AZ (US)
This paper analyzes a postulated loss-of-residual heat removal (RHR) event for a reactor coolant system (RCS) in a midloop condition for the Palo Verde Nuclear Generating Station (PVNGS) using the RETRAN-2/MOD4 computer code. The PVNGS is a Combustion Engineering, two-loop, 3800-MW (thermal) pressurized water reactor (PWR). This analysis was prompted by the U.S. Nuclear Regulatory Commission generic letter 88-17, which requires PWR licensees to perform analyses of loss-of-RHR events for their facilities. Such analyses yield a detailed understanding of loss-of-RHR events and provide a basis for emergency procedures and recovery actions. Simulations of events following a loss of RHR are used to determine the time for RCS coolant to reach boiling, evaluate the potential for a rapid core uncovery due to pressurization of the reactor vessel head with a corresponding liquid ejection from a cold-leg breach, and evaluate options for maintaining the RCS inventory above the core. Key features of the PVNGS midloop condition RETRAN model include isolating both steam generators from the RCS by nozzle dams, setting the initial RCS inventory at midloop, venting the RCS to containment by removing the pressurizer safety relief valves, defining a maintenance breach on one cold leg, and providing options to evaluate makeup water injection to a hot or cold leg by either pump or gravity feed. The RETRAN model provides a satisfactory method for dynamically evaluating loss-of-RHR events from a reduced RCS inventory condition, and for evaluating alternative recovery actions for PVNGS.
- OSTI ID:
- 5080925
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 93:1; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
Similar Records
Core boiling during midloop operation
Simulation of the loss of residual heat removal events during midloop operations
Simulation of the loss of RHR during midloop operations and the role of steam generators in decay heat removal
Journal Article
·
Mon Dec 31 23:00:00 EST 1990
· Nuclear Technology; (United States)
·
OSTI ID:5077645
Simulation of the loss of residual heat removal events during midloop operations
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5372516
Simulation of the loss of RHR during midloop operations and the role of steam generators in decay heat removal
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6982098
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT REMOVAL
CHEMICAL REACTIONS
COMBUSTION
COMPUTER CODES
COOLING SYSTEMS
ENERGY RECOVERY
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
HEAT RECOVERY
HEAT TRANSFER
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXIDATION
PALO VERDE-1 REACTOR
POWER PLANTS
POWER REACTORS
PRESSURIZATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RECOVERY
REMOVAL
RHR SYSTEMS
THERMAL POWER PLANTS
THERMAL REACTORS
THERMOCHEMICAL PROCESSES
US NRC
US ORGANIZATIONS
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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT REMOVAL
CHEMICAL REACTIONS
COMBUSTION
COMPUTER CODES
COOLING SYSTEMS
ENERGY RECOVERY
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
HEAT RECOVERY
HEAT TRANSFER
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXIDATION
PALO VERDE-1 REACTOR
POWER PLANTS
POWER REACTORS
PRESSURIZATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RECOVERY
REMOVAL
RHR SYSTEMS
THERMAL POWER PLANTS
THERMAL REACTORS
THERMOCHEMICAL PROCESSES
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS