RELAP5/MOD3.1 and APROS 3.0 analyses of SBLOCA in scaled VVER-440 geometry
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411842
- VTT Energy (Finland)
A cold-leg small-break loss-of-coolant accident (SBLOCA) experiment was performed on the PACTEL facility to study the behavior of natural circulation in a VVER-440 reactor geometry. The facility is a volumetrically scaled (1:305) integral test loop simulating the VVER-440 reactors used in Finland. The test results were used to assess the computer codes RELAP5/MOD3.1 and APROS 3.0 for VVER reactors. The behavior of the horizontal steam generator and the effect of the hot-leg loop seal were of particular interest. The specific parameters to be compared included the primary pressure and the downcomer mass flow rate.
- OSTI ID:
- 411842
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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