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Computational Perturbation Methods for Moderator and Doppler Temperature Coefficients in the European Pressurised Reactor Core Analysis

机译:欧洲加压反应堆堆芯分析中的慢化和多普勒温度系数的计算摄动方法

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Moderator temperature coefficient (MTC) and fuel Doppler temperature coefficient (DTC) are both the key reactivity coefficients for the safety assessment of a nuclear fission reactor core. Conventional unidirectional perturbing computation exhibits a limited scope in understanding the full-core physics. To better assist the energy policy decision making, this work contributes two different perturbation approaches to characterise the temperature coefficients of reactivity, i.e. by perturbing the moderator (or fuel) temperature while keeping the core power, or by perturbing the power while keeping the moderator (or fuel) temperature. Multi-physics computational codes suite (WIMS-PANTHER-Serpent) is employed to simulate and benchmark the startup core behavior of a nuclear new build currently occurring in the UK. Reasonably good agreements with the nuclear reactor physics are demonstrated computationally for both perturbation methods.
机译:主持人温度系数(MTC)和燃料多普勒温度系数(DTC)都是核裂变反应堆堆芯安全性评估的关键反应系数。常规的单向扰动计算在理解全核物理方面表现出有限的范围。为了更好地协助能源政策决策,这项工作提供了两种不同的扰动方法来表征反应性温度系数,即在保持核心功率的同时扰动慢化剂(或燃料)的温度,或者在保持慢化剂的同时扰动功率(或燃料)温度。多物理量计算代码套件(WIMS-PANTHER-Serpent)用于模拟和基准化英国目前正在发生的核新建筑的启动核心行为。两种扰动方法在计算上都证明了与核反应堆物理学的合理一致。

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