首页> 外文会议>Third Workshop on Utilisation and Reliability of High Power Proton Accelerators (HPPA); May 12-16, 2002; Santa Fe, New Mexico, USA >ACTIVE AND PASSIVE SAFETY CONTROL PERFORMANCE IN SUBCRITICAL, ACCELERATOR-DRIVEN NUCLEAR REACTORS
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ACTIVE AND PASSIVE SAFETY CONTROL PERFORMANCE IN SUBCRITICAL, ACCELERATOR-DRIVEN NUCLEAR REACTORS

机译:次临界,加速器驱动的核反应堆的主动和被动安全控制性能

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Traditional safety performance requirements for nuclear reactors have been developed for critical reactors, whose kinetics characteristics differ significantly from subcritical, accelerator-driven nuclear reactors. In a critical nuclear reactor, relatively small amounts of reactivity (negative or positive) can produce large changes in the fission rate. In subcritical reactors, the self-multiplication (k) decreases as the subcriticality (1-k) increases, and the responsiveness to small reactivity changes decreases. This makes subcritical nuclear reactors less responsive to positive reactivity insertions than critical reactors. Also, larger negative reactivity insertions are needed in subcritical reactors to shut down the fission chain if the neutron source remains. This paper presents the results from a computational analysis of the safety performance of subcritical, accelerator-driven nuclear reactors. Coupled kinetics and thermal-hydraulics models are used to quantify the effectiveness of traditional protection and control system designs in subcritical reactors. The analyses also quantify the role of inherent, passive reactivity feedback mechanisms in subcritical reactors. Computational results are used to develop conclusions regarding the most favourable and effective means for reactor control and protection in subcritical, accelerator-driven nuclear reactors.
机译:对于临界反应堆,已经开发了对核反应堆的传统安全性能要求,其动力学特性与加速器驱动的亚临界核反应堆显着不同。在临界核反应堆中,相对少量的反应性(负或正)可导致裂变率发生较大变化。在亚临界反应堆中,随着亚临界(1-k)的增加,自倍增率(k)降低,并且对小反应性变化的响应性降低。与临界反应堆相比,这使得亚临界核反应堆对正反应性插入的响应性降低。而且,如果保留了中子源,则在次临界反应堆中需要更大的负反应性插入物以关闭裂变链。本文介绍了对亚临界加速器驱动核反应堆安全性能进行计算分析的结果。动力学和热工液压耦合模型用于量化亚临界反应堆中传统保护和控制系统设计的有效性。分析还量化了亚临界反应堆中固有的被动反应性反馈机制的作用。计算结果用于得出有关亚临界加速器驱动核反应堆中最有利和有效的反应堆控制和保护手段的结论。

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