RELAP5/MOD3.1 and APROS 3.0 analyses of SBLOCA in scaled VVER-440 geometry

Journal Article · Sun Dec 31 00:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411842

Riikonen, V; Puustinen, M; Kouhia, J ^[1]

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1. 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-; ISSN 0003-018X; TRN: 97:001087
• Journal Information: Transactions of the American Nuclear Society, Vol. 73; Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995; Other Information: PBD: 1995
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
LOSS OF COOLANT
R CODES
A CODES
PWR TYPE REACTORS
COMPUTER CODES
FLOW RATE
SIMULATION
TWO-PHASE FLOW
STEAM GENERATORS