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A conservative analysis methodology for a steam-line-break accident of the SMART-P plant

机译:SMART-P工厂蒸汽管路破裂事故的保守分析方法

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摘要

The system-integrated modular advanced reactor (SMART) new phase (SMART-P) with a rated thermal power of 65.5 MW is currently being developed at the Korea Atomic Energy, Research Institute. It is an innovative design to achieve a high degree of safety by adopting inherent safety-improving features and passive safety systems. Realistic and conservative calculations and a parameter study for a steam-line pipe break have been carried out by means of the TASS/SMR code. A set of transients for the whole system of SMART-P is investigated from the point of view of fuel integrity. The results of the analyses show that the most conservative initial conditions are thermal design flow, high system pressure, high coolant temperature, and high core power. It is also assumed that off-site power is unavailable and the steam section pipe guillotine break with the least reactive control rod assembly stuck out in the full), withdrawn position is a limiting case under the most moderator density reactivity condition. The SMART-P safety systems function properly and thus secure the reactor to a safe condition with respect to the safety parameters such as the critical heat flux ratio and the pressure. Natural circulation is well established in the primary, and passive residual heat removal systems and is enough to ensure a stable plant shutdown condition after a reactor trips.
机译:韩国原子能研究院目前正在开发额定热功率为65.5 MW的系统集成模块化先进反应堆(SMART)新相(SMART-P)。通过采用固有的安全改进功能和被动安全系统,该创新设计可实现高度安全。借助于TASS / SMR代码,对蒸汽管线的管道破裂进行了现实和保守的计算以及参数研究。从燃料完整性的角度研究了整个SMART-P系统的一组瞬变。分析结果表明,最保守的初始条件是热设计流量,高系统压力,高冷却液温度和高堆芯功率。还假设场外电源不可用,并且蒸汽反应管断头台断裂,而反应性最低的控制杆组件完全伸出,撤出位置是最慢密度反应性条件下的极限情况。 SMART-P安全系统正常运行,因此就安全参数(例如临界热通量比和压力)而言,将反应堆固定在安全条件下。自然循环在主,被动余热去除系统中已经建立,并足以确保反应堆跳闸后稳定关闭工厂。

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