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Safety evaluation of the modified auxiliary feedwater system for the Chinese improved PWR

机译:中国改进型压水堆改进后的辅助给水系统的安全性评估

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摘要

Chinese National Nuclear Safety Administration (NNSA) has issued the general technique requirements of the modification actions for the Nuclear Power Plants (NPPs). The enlargement of the tank volume of the auxiliary feedwater system (ASG) is one of the modification actions to enhance the safety margin for the Chinese improved PWR NPPs. Therefore, it is necessary to evaluate the tank volume of ASG can supply enough cooling water to the secondary side of the steam generators under the transient accidents, to maintain the reactor under safety situation. Typical accident sequences, such as the category Ⅱ accidents of the loss of feedwater (LOFW) with no loss of offsite power (no-LOOP) and the category Ⅳ accidents of the feedwater line break (FWLB) with no-LOOP and the FWLB combined with LOOP, are selected to analyze the minimum flow rate and volume for ASG, based on the RCC-P requirements, based on the model of the typical improved generation Ⅱ 1000 MWe nuclear power plant, built by using the mechanical safety analytical code. The auxiliary feedwater flow rates of 5 m~3/h, 10 m~3/h, 15 m~3/h and 25 m~3/h to each steam generator (SG) for the LOFW with no-LOOP are investigated by analyzing the transient progress, and the results show that the minimum flow rate is 25 m~3/h. FWLB transients with different flow rates of 30 m~3/ h, 35 m~3/h and 45 m~3/h are also analyzed to show that 45 m~3/h is the minimum flow rate considering a safety margin. The minimum volume of the auxiliary feedwater tank is 713 m~3 for the LOFW, 723 m~3 for the FWLB with no-LOOP and 799 m~3 for the FWLB combined with LOOP. Therefore, considering the safety margin, the minimum auxiliary feedwater flow rate necessary to prevent bulk boiling in the reactor coolant system is 45 m~3/h for each unbroken SG, and a 900-m~3 volume of auxiliary feedwater tank can satisfy the RCC-P requirements for the improved PWR NPPs, to give more time to take mitigation measurements.
机译:中国国家核安全局(NNSA)发布了核电厂(NPPs)修改行动的通用技术要求。扩大辅助给水系统(ASG)的水箱容积是为中国改进型压水堆核电厂提高安全裕度的一项改进措施。因此,有必要评估ASG的罐体容量在瞬态事故下能否向蒸汽发生器的二次侧提供足够的冷却水,以确保反应堆处于安全状态。典型的事故序列,例如没有失地电力损失的给水损失(LOFW)Ⅱ类事故(no-LOOP)和没有LOOP和FWLB的给水线路中断的Ⅳ类事故(FWLB)基于RCC-P要求,基于典型的改进型Ⅱ1000 MWe核电厂模型,并使用机械安全分析代码构建,选择具有LOOP的泵来分析ASG的最小流量和体积。对于没有LOOP的LOFW,每个给水蒸汽发生器(SG)的辅助给水流量分别为5 m〜3 / h,10 m〜3 / h,15 m〜3 / h和25 m〜3 / h。分析瞬态过程,结果表明最小流量为25 m〜3 / h。还分析了流量分别为30 m〜3 / h,35 m〜3 / h和45 m〜3 / h的FWLB瞬变,显示45 m〜3 / h是考虑安全裕度的最小流量。 LOFW的辅助给水箱的最小容积为713 m〜3,无LOOP的FWLB的最小容积为723 m〜3,FLOB与LOOP组合的FMBB的最小容积为799 m〜3。因此,考虑到安全裕度,防止反应堆冷却剂系统中大量沸腾所需的最小辅助给水流量对于每个未破损的SG为45 m〜3 / h,并且900-m〜3体积的辅助给水罐可以满足要求。改进的PWR NPP的RCC-P要求,以便有更多时间进行缓解测量。

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