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Experimental Studies for the WER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

机译:可乐NPP的WER-440 / 213气泡冷凝器系统在整体测试设施BC V-213上的实验研究

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摘要

In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3). Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.
机译:在2003年至2005年运行的Tacis项目R2.01 / 99的框架中,可乐NPP(3号机组)的气泡冷凝器系统在整体测试设施BC V-213中进行了认证。进行了三个LB LOCA测试,两个MSLB测试和一个SB LOCA测试。通过预测试计算确定了BC V-213测试设备的适当测试方案,即在可乐NPP 3号机组中模拟事故。对测试结果的分析表明,在测试中正确再现了计算的初始条件和测试方案。在BC V-213测试设备上进行的测试的详细后测试分析旨在验证COCOSYS代码,以计算密闭隔室和气泡冷凝器中的热工过程。之后,将经过验证的COCOSYS代码应用于Kola NPP(单元3)的NPP计算。 Tacis R2.01 / 99项目的结果证实了大和小断裂LOCA和MSLB事故期间的气泡冷凝器功能。在LB LOCA情况下达到了最大负载。没有观察到冷凝振荡。

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  • 来源
    《Science and technology of nuclear installation》 |2012年第1期|p.275693.1-275693.20|共20页
  • 作者单位

    Thermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants,Saint Constantine Street 6, Electrogorsk, Moscow 142530, Russia;

    Thermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants,Saint Constantine Street 6, Electrogorsk, Moscow 142530, Russia;

    Thermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants,Saint Constantine Street 6, Electrogorsk, Moscow 142530, Russia;

    Thermo-Hydraulics Division, Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants,Saint Constantine Street 6, Electrogorsk, Moscow 142530, Russia;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Kurfuerstendamm 200,10719 Berlin, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Kurfuerstendamm 200,10719 Berlin, Germany;

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