Simulation of a loss-of-coolant accident in a WWER reactor - an IAEA standard problem exercise
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6897904
In order to enlarge the experimental data base for code assessment, the International Atomic Energy Agency (IAEA), in cooperation with the Central Research Institute for Physics of the Hungarian Academy of Sciences, has organized a standard problem exercise involving the simulation of a loss-of-coolant accident (LOCA) in the PMK-NVH experimental facility, a scaled-down model of a WWER-440 nuclear power plant. This paper presents a description of the facility and the test and summarizes the conclusions of the intercomparison of results provided by the 17 participants in pretest and post-test calculations.
- OSTI ID:
- 6897904
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- 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
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DRYOUT
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
IAEA
INTERNATIONAL ORGANIZATIONS
LOSS OF COOLANT
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SIMULATION
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DRYOUT
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
IAEA
INTERNATIONAL ORGANIZATIONS
LOSS OF COOLANT
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SIMULATION
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS