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

Jinfeng Li
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引用次数: 8

Abstract

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.
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欧洲压堆堆芯分析中慢化剂和多普勒温度系数的计算摄动方法
慢化剂温度系数(MTC)和燃料多普勒温度系数(DTC)都是核裂变堆芯安全评价的关键反应性系数。传统的单向摄动计算在理解全核物理方面表现出有限的范围。为了更好地辅助能源政策决策,本研究提出了两种不同的扰动方法来表征反应性的温度系数,即在保持堆芯功率的同时扰动慢化剂(或燃料)温度,或在保持慢化剂(或燃料)温度的同时扰动功率。多物理场计算代码套件(wwin - panther - serpent)用于模拟和基准测试当前在英国发生的新核构建的启动核心行为。计算结果表明,这两种微扰方法与核反应堆物理特性相当吻合。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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