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A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

机译：评估先进气冷堆石墨组分中子损伤和核能沉积的三维方法

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摘要

This paper describes the development of a three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition (or nuclear heating) throughout the graphite cores of the UK's Advanced Gas-cooled Reactors. Advances in the development of the Monte Carlo radiation transport code MCBEND have enabled the efficient production of detailed fully three-dimensional models that utilise three-dimensional source distributions obtained from Core Follow data supplied by the reactor physics code PANTHER. The calculational approach can be simplified to reduce both the requisite number of intensive radiation transport calculations, as well as the quantity of data output. These simplifications have been qualified by comparison with explicit calculations and they have been shown not to introduce significant systematic uncertainties. Simple calculational approaches are described that allow users of the data to address the effects on neutron damage and nuclear energy deposition predictions of the feedback resulting from the mutual dependencies of graphite weight loss and nuclear energy deposition.
机译：本文介绍了一种用于评估英国先进气冷堆整个石墨核中子损伤和核能沉积（或核加热）的三维方法的发展。蒙特卡罗辐射传输代码MCBEND的开发进展使得能够有效生成详细的完整三维模型，该模型利用了从反应堆物理代码PANTHER提供的Core Follow数据获得的三维源分布。可以简化计算方法，以减少密集辐射传输计算所需的次数以及数据输出的数量。通过与显式计算进行比较，可以简化这些简化操作，并且已证明这些简化操作不会带来重大的系统不确定性。描述了简单的计算方法，这些方法使数据的用户能够解决由于石墨失重与核能沉积之间的相互依赖性而产生的反馈对中子破坏和核能沉积预测的影响。

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