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THE IMPACT OF POWER COEFFICIENT OF REACTIVITY ON CANDU 6 REACTORS

机译:反应性功率系数对CANDU 6反应器的影响

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摘要

The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions. The Power Coefficient of Reactivity (PCR) is an aggregate indicator representing the change in reactor core reactivity per unit change in reactor power. It is an integral quantity which captures the contributions of the fuel temperature, coolant void, and coolant temperature reactivity feedbacks. All nuclear reactor designs provide a balance between their inherent nuclear characteristics and the engineered reactivity control features, to ensure that changes in reactivity under all operating conditions are maintained within a safe range. The CANDU~® reactor design takes advantage of its inherent nuclear characteristics, namely a small magnitude of reactivity coefficients, minimal excess reactivity, and very long prompt neutron lifetime, to mitigate the demand on the engineered systems for controlling reactivity and responding to accidents. In particular, CANDU reactors have always taken advantage of the small value of the PCR associated with their design characteristics, such that the overall design and safety characteristics of the reactor are not sensitive to the value of the PCR. For other reactor design concepts a PCR which is both large and negative is an important aspect in the design of their engineered systems for controlling reactivity. It will be demonstrated that during Loss of Regulation Control (LORC) and Large Break Loss of Coolant Accident (LBLOCA) events, the impact of variations in power coefficient, including a hypothesized larger than estimated PCR, has no safety-significance for CANDU reactor design. Since the CANDU 6 PCR is small, variations in the range of values for PCR on the performance or safety of the reactor are not significant.
机译:反应系数的综合作用以及其他堆芯核特性决定了反应堆堆芯在正常运行和事故情况下的行为。反应堆功率系数(PCR)是代表反应堆功率每单位变化的反应堆堆芯反应性变化的综合指标。它是一个积分量,可捕获燃料温度,冷却液空隙和冷却液温度反应性反馈的影响。所有核反应堆设计均在其固有核特征与工程反应性控制特征之间取得平衡,以确保在所有运行条件下反应性的变化均保持在安全范围内。 CANDU〜®反应堆设计利用了其固有的核特性,即反应性系数小,最小的过量反应性和非常长的中子寿命,可减轻对工程系统控制反应性和应对事故的需求。特别地,CANDU反应器一直利用与其设计特征相关的PCR的小值,使得反应器的整体设计和安全特征对PCR的值不敏感。对于其他反应器设计概念,在控制反应性的工程系统设计中,PCR既大又阴性。将会证明,在失去调节控制(LORC)和大断裂冷却剂事故(LBLOCA)事件期间,功率系数变化的影响(包括假设大于估计的PCR的影响)对CANDU反应堆设计没有安全意义。 。由于CANDU 6 PCR较小,因此PCR值范围对反应器性能或安全性的影响不明显。

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  • 来源
    《Nuclear engineering and technology》 |2013年第5期|573-580|共8页
  • 作者单位

    Candu Energy Inc 2285 Speakman Drive, Mississauga, ON, L5K 1B1 Canada;

    Candu Energy Inc 2285 Speakman Drive, Mississauga, ON, L5K 1B1 Canada;

    Candu Energy Inc 2285 Speakman Drive, Mississauga, ON, L5K 1B1 Canada;

    Korea Atomic Energy Research Institute 989-111, Daedeok-daero, Yuseong-gu, Daejeon, Korea;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    PCR; FTCR; CANDU; LORC; LOCA; Safety;

    机译:PCR;FTCR;坎杜;LORC;LOCA;安全;

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