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INFLUENCE OF LOW BORON CORE DESIGN ON PWR TRANSIENT BEHAVIOR

机译:低硼核设计对压水堆瞬态行为的影响

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摘要

In conventional pressurized water reactor (PWR) designs, the concentration of boron in primary coolant is limited by the requirement of having a negative moderator density coefficient. As high boron concentrations have significant impact on reactivity feedback properties, design changes to reduce boron concentration in the reactor coolant are of general interest in view of improving PWR inherent safety. In the framework of an investigation into the feasibility of low boron design, a PWR core configuration based on fuel with higher gadolinium (Gd) content has been developed which permits to reduce the natural boron concentration at begin of cycle (BOC) by approx. 50% compared to current German PWR technology. For the assessment of the potential safety advantages, a Loss-of-Feedwater Anticipated Transient Without Scram (ATWS LOFW) has been simulated with the system code ATHLET for two PWR core designs: a low boron design and a standard core design. The most significant difference in the transient performance of both designs is the total primary fluid mass released through the pressurizer (PRZ) valves. It is reduced by a factor of four for the low boron reactor, indicating its improved density reactivity feedback.
机译:在常规的压水反应堆(PWR)设计中,一次冷却剂中硼的浓度受到负负慢化剂密度系数的限制。由于高硼浓度会对反应性反馈性能产生重大影响,因此从降低PWR固有安全性的角度出发,旨在降低反应堆冷却剂中硼浓度的设计更改已引起广泛关注。在研究低硼设计可行性的框架内,已经开发了一种基于with含量较高的燃料的压水堆堆芯配置,该结构可将循环开始时的自然硼浓度降低约50%。与目前的德国PWR技术相比,降低了50%。为了评估潜在的安全优势,已使用系统代码ATHLET对两种PWR堆芯设计进行了模拟无给水预期的无扰动瞬态(ATWS LOFW):低硼设计和标准堆芯设计。两种设计的瞬态性能中最显着的差异是通过增压器(PRZ)阀释放的总一次流体质量。对于低硼反应器,它减少了四倍,表明其密度反应性反馈得到了改善。

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