首页> 外文会议>International Congress on Advances in Nuclear Power Plants >PARAMETER CHANGES IN CORE DESIGNS AND SAFETY ANALYSES DUE TO POWER UPRATE FOR KORI 34 AND YONGGWANG 12
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PARAMETER CHANGES IN CORE DESIGNS AND SAFETY ANALYSES DUE TO POWER UPRATE FOR KORI 34 AND YONGGWANG 12

机译:核心设计和安全分析的参数变化由于KORI 3和4和永冠1和2的电源UPRATE

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Power uprate of 4.5percent is accomplished first for Kori 3&4 (KRN 3&4) and Yonggwang 1&2 (YGN 1&2) in Korea. This is categorized as a stretch power uprate, and generally the primary systems are not modified because it can be achieved by the originally possessed system margins, while the secondary systems or components are improved or replaced to accommodate the increased core power. Thus, investigation and evaluation of system, safety and operation parameters in the primary systems are one of the major tasks to achieve the stretch power uprate. This paper describes the parameter changes due to the power uprate of 4.5percent and evaluation efforts by core designs and safety analyses to implement it into KRN 3&4 and YGN 1&2. The power uprate of 4.5percent is determined through the feasibility study so that core power is increased from 2,775 to 2,900 MWt, while RCS pressure is maintained at 2,250 psia. Thermal design flow and RCS average temperature are reduced by 1.5percent and 2.5 deg F to compensate the degraded RCS flow rate and to keep the hot leg temperature the same, respectively. Physics design is carried out and the results show that most physics parameters are within typical variations at the current reload design. However, three input parameters to safety analyses such as most positive moderator density coefficient, F_(Q) at EOC, hot zero power for rod ejection accident and axial flux difference limit must be changed to accommodate the increased power. Thermal hydraulic design demonstrates that thermal hydraulic stability of the core can be maintained. DNBR is calculated using a statistical thermal design procedure and determines as 1.25 for design limit DNBR at the hottest rod, 1.45 for safety analysis limit DNBR and 2.53 for minimum DNBR at normal operation, which are decreased from 1.35, 1.71 and 2.66 respectively to accommodate the increased power. Evaluations of fuel rod and fuel assembly designs confirm that their performance and integrity are within related design criteria. Non-LOCA analyses are carried out using the current methodologies and all analyses results show compliance with the acceptance criteria even though they move in close to the limit due to the increased power. KREM which is a realistic evaluation model is newly applied to LBLOCA analysis and PCT is reduced from 2,091 to 2,032 deg F despite considering the power uprate conditions. SBLOCA and long term cooling analyses are carried out using the current methodologies and all results are within the criteria. Core designs and safety analyses are successfully completed and it is demonstrated that their results are appropriate and acceptable for power uprate of 4.5percent. And, electrical gains are 3.4percent for KRN 3&4 and 5.0percent for YGN 1&2 due to HP turbine diaphragm replacement and HP turbine retrofit, respectively.
机译:4.5平方的电源UPRATE首先为韩国的KORI 3和4(KRN 3和4)和永冠1和2(YGN 1&2)完成。这被分类为拉伸电源Uprate,并且通常,主要系统不会被修改,因为它可以通过最初具有系统的系统利润来实现,而辅助系统或部件得到改善或更换以适应增加的核心电源。因此,主系统中的系统,安全和操作参数的调查和评估是实现拉伸电源uprate的主要任务之一。本文介绍了由于核心设计和安全性分析的4.5平方和评估工作,以将其实施到KRN 3和YGN 1&2,因此介绍了引起的参数变化。通过可行性研究确定4.5的电源UPRATE。核心功率从2,775增加到2,900 MWT,而RCS压力保持在2,250psia。热设计流程和RCS平均温度减少1.5%和2.5°F以补偿降低的RCS流速并分别保持热腿温度。物理设计进行了,结果表明,大多数物理参数都在当前刷新设计的典型变化范围内。然而,三个输入参数为安全分析,例如大多数正面主持人密度系数,F_(Q),用于杆喷射事故的热零功率和轴向磁通差极限,以适应增加的功率。热液压设计表明,可以保持芯的热液压稳定性。 DNBR使用统计热设计程序计算,并在最热棒中确定为1.25,在最热杆上设计限制DNBR,1.45用于安全分析限制DNBR和2.53的正常运行中的最小DNBR,分别从1.35,1.71和2.66减少以容纳才能容纳增加力量。燃料棒和燃料组件设计的评估证实它们的性能和完整性在相关的设计标准中。使用当前方法进行非LOCA分析,并且所有分析结果表明,即使它们由于增加的功率而靠近限制,它们也表现出符合验收标准。作为一个现实评估模型的KREM新应用于Lbloca分析,并且尽管考虑到电动上起伏条件,但PCT减少了2,091至2,032°F。使用当前方法进行SBLOCA和长期冷却分析,所有结果都在标准内。核心设计和安全分析成功完成,并证明其结果是适当的,适用于4.5%的电源uprate。并且,由于HP涡轮机隔膜更换和HP涡轮机改装,电气收益为KRN 3&4和5.0为YGN 1和2.0为YGN 1和2。

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