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压力温度限值曲线计算与比较分析 预览 被引量:2

Calculation and Comparison of Pressure-Temperature Limit Curves Calculation
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摘要 核电厂在启停堆过程中必须将压力和温度控制在限值范围内,即压力温度限值曲线(P-T曲线)所允许的范围内,以防止反应堆压力容器发生脆性开裂。以法国的RCCM规范、美国的ASME规范和我国的核行业标准EJ/T918为对象,对比分析P-T曲线各自的计算方法,讨论了所采用的保守假设对计算结果的影响。研究表明,选取材料静态断裂韧性KIC计算P-T曲线将会增加核电厂启停堆过程中的操控空间;与最新版国外规范比较,我国行业标准EJ/T918的计算结果显得过于保守。 In order to prevent the brittle fracture, during nuclear power plant (NPP) heatup and cooldown processes, pressure and temperature in the reactor pressure vessel should be kept under the pressure-temperature (P-T) limit curve. In this paper, the P-T limit curve methodologies of ASME code, RCCM code and Chinese Nuclear Industry Standard EJ/T 918 are studied. Calculation and comparison of the P-T curves obtained using methods from different codes are performed. It shows that using static fracture toughness KIC instead of reference fracture toughness KIR to calculate the P-T curves increases acceptable operating region during NPP heatup and cooldown processes significantly. Comparing to the latest versions of ASME and RCCM codes, the Chinese standard is more conservative.
作者 吕峰 钱海洋 王荣山 黄平 LU Feng, QIAN Hai-yang, WANG Rong-shan, HUANG Ping 1. Suzhou Nuclear Power Research Institute, Suzhou, Jiangsu, 215004, China; 2. Structural Integrity Associates, Inc. San Jose, USA
出处 《核动力工程》 EI CAS CSCD 北大核心 2012年第3期65-68,共4页 Nuclear Power Engineering
基金 江苏省自然科学基金(BK2009560) 苏州市(金阊区)2011年度科技计划项目
关键词 反应堆压力容器 压力温度限值曲线 辐照脆化 Reactor pressure vessel, Pressure temperature limit curve, Irradiation embrittlement
作者简介 吕峰(1978-),男,博士。2008年毕业于大连理工大学工程力学专业,获工学博士学位。现主要从事核电站压力容器结构完整性分析。 钱海洋(1978-),男,博士。2008年毕业于美国Purdue大学航空航天学院,获博士学位。现主要从事核电站压力容器及管道的结构完整性分析。 王荣山(1973-),男,博士。2009年毕业于北京科技大学材料专业,获工学博士学位。现主要从事反应堆压力容器寿命管理工作。
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参考文献7

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同被引文献10

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  • 10吕峰,陈明亚.反应堆压力容器压力-温度限值曲线参数敏感性分析[J].工程力学,2013,30(2):394-399. 被引量:2

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