RELAP5 simulation of SB LOCA in a VVER 440 model
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6660346
The VVER-440-type plants differ considerably from western-type pressurized water reactors (PWR). The two main distinguishing characteristics are horizontal steam generators and loop seals in both hot and cold legs, which are lately a great safety concern worldwide. In 1987, the International Atomic Energy Agency (IAEA) organized and sponsored one of the tests performed on the Hungarian PMK-NVH test facility and called it IAEA-SPE-2. The test was chosen from a wider test matrix performed to investigate emergency core cooling system capability in VVER-440 plants for a small-break loss-of-coolant accident (SB LOCA). PMK-NVA is a one-loop, full-height, full-pressure model of the Hungarian Paks nuclear power plant, type VVER-440, Soviet production. The facility power level is 100%, according to the 1:2070 scaling factor.
- OSTI ID:
- 6660346
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
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REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
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THERMAL REACTORS
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WATER COOLED REACTORS
WATER MODERATED REACTORS