Fission product release during a LOCA in VVER-440/213-type reactor

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7022210

Sdouz, G ^[1]

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1. Austrian Research Ctr., Seibersdorf (Austria)

In 1988, Austria initiated a research program to investigate the source term behavior of VVER-type reactors. Mainly, there are three design categories for VVER-type reactors. The first standardized 440-MW(electric) nuclear power plant was designated as VVER-440/MW(electric) nuclear power plant was designated as VVER-440/230. A somewhat more advanced model was designated as model V213. These reactors have six loops, isolation valves on each loop, horizontal steam generators, and hexagonal fuel assemblies. To prevent the release of fission products, the concept of local area compartmentalization is applied. The main difference between the two models is the existence of an emergency core cooling system (ECCS) and a bubbler-condenser tower in the newer model. In the 1970s, a 1000-MW(electric) reactor was designed and designated as VVER-1000. This unit has four loops housed in a containment-type structure with spray-type steam suppression. The Austrian program started with source term calculations for the VVEr-1000-type reactor. A TMLB{prime} and a S{sub 1}B accident sequence were calculated using the Source Term Code Package (STCP). In 1990, the source term analyses were extended to both models of the VVER-440-type reactors. In this paper, the results of the thermohydraulic part of the calculation for the VVER-440/213 reactor are presented.

• OSTI ID: 7022210
• Report Number(s): CONF-911107-; CODEN: TANSA; TRN: 92-030856
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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LOSS OF COOLANT
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CONTAINMENT SPRAY SYSTEMS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL ASSEMBLIES
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ENRICHED URANIUM REACTORS
EUROPE
FLUIDS
GASES
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NONMETALS
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RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
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THERMAL REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
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