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Benchmark study of 10 MW_(th) Material Test Reactor by standard deterministic codes

机译:基准的研究10 MW_ (th)材料试验反应堆的标准确定的代码

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摘要

A static, full core calculation for IAEA 10 MW_(th) Material Test Reactor (MTR) benchmark problem is carried out using a standard set of computer code systems, namely: (i) WIMSD/4, TWOTRAN and NEMSQR and (ii) DRAGON and NEMSQR. The current work focuses on the evaluation of various important neutronic parameters such as neutron multiplication factor, reactivity feedback coefficients, reactivity worth of control devices, etc. of the IAEA 10 MW_(th) MTR benchmark reactor, using the above code systems. The IAEA 10 MW_(th) benchmark problem is useful for testing the ability of a code to reliably simulate a compact, highly heterogeneous core made up of U235-enriched fuel in plate-type geometry. The study is carried out to validate the calculation methodology currently adopted by us for plate-type fuel assemblies and compact reactor cores while using these standard computer codes.
机译:一个静态的,完整的国际原子能机构的核心计算10MW_ (th)材料测试反应堆(地铁)基准问题是使用一组标准的计算机代码系统,即:(i) WIMSD / 4,当前关注的评估工作各种重要的中子的参数等中子倍增系数、反应性反馈系数、反应性的价值国际原子能机构的控制装置等10 MW_ (th)地铁基准反应堆,使用上面的代码系统。国际原子能机构10 MW_ (th)基准问题是有用的可靠地测试代码的能力模拟一个紧凑的、高度异构的核心由U235-enriched燃料在平板型几何学。目前采用的计算方法我们为平板式燃料组件和紧凑反应堆堆芯在使用这些标准的电脑代码。

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