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VERA BENCHMARKING RESULTS FOR KRSKO NUCLEAR POWER PLANT CYCLE 1

机译:KRSKO核电站1的VERA基准测试结果

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The Consortium for Advanced Simulation of Light Water Reactors (CASL), the first US Department of Energy (DOE) Innovation Hub, has developed a high-fidelity suite of methods and software for engineering analyses of commercial nuclear power plants. The Virtual Environment for Reactor Applications (VERA) has been successfully developed and applied to several reactor types operated or designed by CASL partners. To broaden its validation basis, VERA was applied to the Nuklearna elektrarna Krsko, a European two-loop Westing-house-designed pressurized water reactor (PWR) with 16×16 fuel. VERA enables multigroup deterministic and continuous-energy Monte Carlo neutron transport for the entire reactor using the same basic input and output features. Deterministic methods are directly coupled to a two-phase subchannel thermal-hydraulic method and an in-line isotopic decay and depletion module for 3D whole-core power distribution and fuel depletion analyses. VERA's performance for full core calculations is documented, and the results are compared to measured critical boron concentrations, startup physics tests results, and measured radial power distributions from Krsko Cycle 1. Results are also compared to calculations from the Jozef Stefan Institute (JSI) CORD-2 package routinely used for verification of the Krsko reload cores. Finally, comparisons are made for a set of 2D lattice depletions performed by Serpent and Polaris for additional verification.
机译:该联盟用于光水反应器(CASL)的先进模拟,美国第一家能源部(DOE)创新枢纽开发了一种高保真套件,用于商业核电站的工程分析。 Reactor应用程序(VERA)的虚拟环境已成功开发并应用于Casl Partners操作或设计的多种电抗器类型。为了扩大其验证基础,Vera应用于Nuklearna Elektrarna Krsko,欧洲双环西泠印社设计的加压水反应堆(PWR),具有16×16燃料。 Vera使用相同的基本输入和输出功能使整个电抗器的MultiGroup确定型和连续能量蒙特卡罗中子传输。确定性方法直接耦合到两相子沟槽热液压方法和线上同位素衰减和耗尽模块,用于3D全核配电和燃料耗尽分析。 VERA对全核计算的性能进行了记录,并将结果与​​测量的致力硼浓度进行比较,启动物理测试结果,以及来自KRSKO周期的测量径向电力分布。结果也与Jozef Stefan Institute(JSI)绳索的计算进行了比较-2包常规用于验证KRSKO重新加载核心。最后,对由蛇和极性进行的一组2D晶格耗尽进行比较,以进行额外验证。

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