| 压力温度限值曲线计算与比较分析 |
| |
| 引用本文： | 吕峰,钱海洋,王荣山,黄平.压力温度限值曲线计算与比较分析[J].核动力工程,2012,33(3):65-68. |
| |
| 作者姓名： | 吕峰 钱海洋 王荣山 黄平 |
| |
| 作者单位： | 1. 苏州热工研究院,江苏苏州,215004
2. Structural Integrity Associates, Inc. San Jose, USA |
| |
| 基金项目： | 江苏省自然科学基金，苏州市(金阊区)2011年度科技计划项目 |
| |
| 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。
|
| 关 键 词： | 反应堆压力容器 压力温度限值曲线 辐照脆化 |
Calculation and Comparison of Pressure-Temperature Limit Curves Calculation |
| |
| LU Feng
,
QIAN Hai-yang
,
WANG Rong-shan
,
HUANG Ping.Calculation and Comparison of Pressure-Temperature Limit Curves Calculation[J].Nuclear Power Engineering,2012,33(3):65-68. |
| |
| Authors: | LU Feng QIAN Hai-yang WANG Rong-shan HUANG Ping |
| |
| Affiliation: | 1.Suzhou Nuclear Power Research Institute,Suzhou,Jiangsu,215004,China;2.Structural Integrity Associates,Inc.San Jose,USA |
| |
| Abstract: | 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. |
| |
| Keywords: | Reactor pressure vessel Pressure temperature limit curve Irradiation embrittlement |
| 本文献已被 CNKI 万方数据 等数据库收录！ |
|
