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首页> 外文期刊>Annals of nuclear energy >Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design
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Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design

机译:使用OECD / NEA MHTGR-350核心设计的简化模型来验证热流体分析代码的基准计算

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Sponsored by the OECD/NEA, a benchmark study on prismatic high temperature gas-cooled reactor (HTGR) using the MHTGR-350 design was initiated. One of the important lessons learned during the process of Phase 1 Exercise 2 of the OECD/NEA MHTGR-350 benchmark is that even the simplest benchmark case of Phase 1 Exercise 2 is too complex to identify reasons for differences among the results obtained by different computer codes. In this work, therefore, simpler benchmark test cases have been developed to improve the efficiency of the verification process of thermo-fluid analysis codes to simulate a prismatic HTGR core. Retaining the major physical thermo-fluid phenomena, the original OECD/NEA benchmark model of Phase 1 Exercise 2 was simplified and four test cases were established using well-organized boundary conditions. Numerical simulations using three computer codes (i.e., GAMMA+, AGREE, and CFX) were performed and good agreement was achieved among the results obtained by the three codes. It is believed that the proposed benchmarks are particularly helpful for code developers and/or researcher who attempt to solve the official MHTGR-350 Benchmark for the first time. (C) 2019 Elsevier Ltd. All rights reserved.
机译:由经合组织/国家能源局赞助的一项关于使用MHTGR-350设计的棱柱形高温气冷堆(HTGR)的基准研究已经启动。在OECD / NEA MHTGR-350基准测试的第一阶段练习2的过程中,获得的重要教训之一是,即使最简单的基准测试案例1的第二阶段也太复杂了,无法确定使用不同计算机获得的结果之间存在差异的原因。代码。因此,在这项工作中,已经开发了更简单的基准测试用例,以提高热流体分析代码的验证过程的效率,以模拟棱柱形HTGR核。为了保留主要的物理热流体现象,简化了第一阶段练习2的原始OECD / NEA基准模型,并使用井井有条的边界条件建立了四个测试用例。使用三种计算机代码(即GAMMA +,AGREE和CFX)进行了数值模拟,并且在这三种代码获得的结果之间取得了很好的一致性。可以相信,建议的基准对于首次尝试解决MHTGR-350官方基准的代码开发人员和/或研究人员特别有用。 (C)2019 Elsevier Ltd.保留所有权利。

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