Simulation of loss-of-decay heat removal with MAAP 3. 0B
Loss-of-decay heat removal (DHR) during nonpower operation and its potential consequences have been of increasing concern to US pressurized water reactor (PWR) owners and regulators. Regulatory action prompted by the April 10, 1987, loss of DHR at Diablo Canyon Unit 2 cited 37 instances of loss of DHR events attributed to inadequate reactor coolant system (RCS) water level. In the Diablo Canyon event, 7 days after shutdown for its first refueling outage, boiling and pressurization of the primary system began after {approximately}1 h after loss of DHR, which was reestablished after another 20 min. This paper describes the modification and application of the Modular Accident Analysis Program (MAAP) version 3.0B (Ref. 3) for simulation of loss of DHR scenarios. MAAP 30.B, maintained by the Electric Power Research Institute and available to most US and many foreign utilities, is designed to perform coupled thermal-hydraulic and fission product calculations for severe-accident analysis. In this application, the capabilities of MAAP are extended to allow simulation of a shutdown plant state to calculate the time to core uncovery and fuel damage. Operator actions to mitigate or terminate the accident can be simulated, and timing of key events given by MAAP is useful for the evaluation of procedures.
- OSTI ID:
- 6528899
- Report Number(s):
- CONF-891103--
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Improvements to MAAP 3. 0B for IPE (individual plant evaluations) analyses
Simulation of Phases 3 and 4 of the TMI-2 accident using MAAP-DOE and MAAP 3. 0B, Task 3. 9
Related Subjects
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
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BOILERS
CAVITATION
COMPUTER CODES
COMPUTERIZED SIMULATION
CONVECTION
COOLING SYSTEMS
DIABLO CANYON-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPRI
FAILURES
FEEDWATER
FISSION PRODUCT RELEASE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LEVELS
M CODES
MAINTENANCE
MASS TRANSFER
MECHANICS
MODIFICATIONS
NATURAL CONVECTION
OXYGEN COMPOUNDS
PERSONNEL
POWER REACTORS
PRESSURIZATION
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR FUELING
REACTOR MAINTENANCE
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
REGULATIONS
REMOVAL
RHR SYSTEMS
SAFETY
SECONDARY COOLANT CIRCUITS
SHUTDOWN
SIMULATION
STEAM GENERATORS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS