PSB-VVER experimental and analytical investigation of station blackout accident in VVER-1000
Creators
- 1. Electrogorsk Research and Engineering Centre (EREC), Moscow Region (Russian Federation)
- 2. NSI RRC, Kurchatov Institute, Moscow (Russian Federation)
Description
In November 2003, an experiment simulating station blackout accident was carried out in the PSB-VVER integral test facility at the Electrogorsk Research and Engineering Centre (Russia). The purpose of the experiment was to provide missing data for code validation as well as to investigate the VVER thermohydraulics in the blackout conditions. The experiment covers a wide range of phenomena relating not only to transients but also to small break loss-of-coolant accidents. The data gained in the test has been used to assess the RELAP5/MOD3.3 code. In this paper, a special attention has been paid to the code assessment regarding the mixture level and entrainment in steam generator secondary side. The analysis of the recorded transient has shown that the calculation of the heat transfer on the secondary side of steam generators is very sensitive to the steam generator nodalization. (authors)
Availability note (English)
Available from: SFEN, 5 rue des Morillons, 75015 Paris (France)Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- INIS-FR--08-0525
Conference
- Title
- ICAPP 2007 - International congress on advances in nuclear power plants. The nuclear renaissance at work
- Dates
- 13-18 May 2007
- Place
- Nice Acropolis (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 39050480
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- HEAT TRANSFER; LOSS OF COOLANT; OUTAGES; R CODES; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY EXPERIMENTS; TEST FACILITIES; TRANSIENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.