ICONE11-36335 ANALYSIS OF 200mm LOCA AT ARMENIAN NPP UNIT 2

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概要

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• Analyses of a loss-of-coolant accident (LOCA) in primary side were performed for Armenian Nuclear Power Plant (ANPP) using the RELAP5 code, with break sizes of the equivalent diameter of 200 mm. ANPP is a six-loop WWER-440/270 model of Russian design. In the Technical Assignment for WWER-440/270 reactors, LOCAs were analyzed for break sizes up to 0.0078 m^2 (equivalent diameter of about 100 mm). Results show that this reactor has relatively high safety margins with 100 mm LOCAs, which may allow increasing the safety level for the maximum design base LOCA. The definition of the maximal design accident is based on actual rupture of any pipeline. In the primary circuit of the ANPP there are two pipelines with 200mm diameter. These are two pressurizer surge lines. In order to increase the maximal design base accident with loss-of-coolant event for break size up to 200mm it is sufficient to consider one pipeline break of the pressurizer surge lines. The purpose of the analyses was to demonstrate the adequacy of the safety margin in relation to a loss-of-coolant event in different pipelines of primary side with equivalent diameter of 200 mm using the existing high-pressure injection system. The breaks of the pressurizer surge line and breaks with equivalent diameter of 200 mm on main circulation pipelines have been analyzed. The Mod3.2.2β version of RELAP5 was used for the analyses. The analyses were carried out on the basis of conservative approaches in terms of the reactor core cooling. According to WWER design approach, a loss of off-site power was assumed at the moment of accident beginning and simultaneous reactor scram. Diesel generators were assumed to be available 20 seconds after off-site power loss and their operation was assumed to take into account single failure principle. The results of LOCA analyses with conservative assumptions show that the acceptance criteria were not exceeded in case of surge line break. However in case of break with equivalent diameter of 200 mm on a cold leg the cladding temperature exceeded the safety limit.

• 一般社団法人日本機械学会の論文

著者

• Jo Jae

  Brookhaven National Laboratory

• Amirjanyan Armen

  Nuclear & Radiation Safety Center of Armenian Nuclear Regulatory Authority

• Malakyan Tsolak

  Nuclear & Radiation Safety Center of Armenian Nuclear Regulatory Authority

• Malakyan Tsolak

  Nuclear & Radiation Safety Center Of Armenian Nuclear Regulatory Authority

• Amirjanyan Armen

  Nuclear & Radiation Safety Center Of Armenian Nuclear Regulatory Authority

関連論文

• ICONE11-36335 ANALYSIS OF 200mm LOCA AT ARMENIAN NPP UNIT 2

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