中国实验快堆高温钠管道蠕变分析方法研究
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摘要
中国实验快堆(CEFR)正在紧张建造中。其堆中有许多影响反应堆安全运行的高温钠管道将承受长期的高温交变载荷(压力交变和温度交变)，而钠冷快堆高温管道设计和结构分析技术是快堆发展多年以来的瓶颈技术，也是目前影响中国实验快堆工程进度的重要技术难题之一。为了确保反应堆的安全运行，必须对承受长期高温热循环载荷的钠管道进行高温疲劳和蠕变分析，进而完善中国实验快堆高温钠管道的安全分析和寿命评估，为CEFR安全运行寿命研究提供技术基础。
本文针对该问题的国内外研究现状，紧密结合工程建设的需要，应用CASTEM2000软件，对中国实验快堆的事故余热排放系统的热段钠管道进行了详细的数值模拟和研究，以探寻一种合适的研究中国实验快堆高温钠管道蠕变的分析方法。主要内容如下：
通过运用2002版RCC-MR《快中子增殖堆核岛机械设备设计和建造规则》标准和CASTEM2000计算程序，采用线弹性分析理论对中国实验快堆的事故余热排放系统的热段钠管道进行详细的应力分析与评定，包括管道强度计算，管道变形分析，管道支撑受力分析(静载荷分析)，以及在整个工作寿期内的总体应变和疲劳——蠕变分析。首次完成了对超过材料蠕变温度的高温钠管道的高温蠕变分析，为此段钠管道的安全运行提供了技术上的保证，同时其分析结果对日后快堆高温钠管道的蠕变应变测量和在役检查提供参考；并且本论文对RCC-MR规范的运用也对中国钠冷快中子增殖堆的高温管道设计标准的建立提供依据。
China Experimental Fast Reactor(CEFR) is under construction. There are many high temperature sodium pipes important to safety of CEFR, which they are have the hot temperature and long time of the thermal cycle in the total operating period. But this issue is one of the important technologic problem to effect the construction of CEFR. In order to ensure the safety of fast reactor, it is important and necessary to analyses to prevent the different kinds of damages, appraisal of progressive deformation, fatigue and creep assessment.
Upon the investigation on the domestic and foreign status of this issue, and according to the situation of CEFR, the detailed numerical analysis about high temperature sodium pipe of the accident excess heat discharging system can find out the way to research the high temperature creep of CEFR, and then the program of CASTEM2000 will be used to stress calculation. The major researches are outlined as the following:
The detailed stresses are calculated using the linear elastic beams method about high temperature sodium pipe of the accident excess heat discharging system. The mechanical calculations are based on those results and respect the rules of the RCC-MR Edition 2002, and then the program of CASTEM2000 is used to stress calculation. The pipe analysis is included which type of damage, reactions of supports (dynamic loading is not taken into account), negligible creep or significant creep and creep-fatigue calculation according to the segment of pipe's loading and boundary conditions during the total period. This segment of sodium pipe analysis can not only provide the safety of CEFR, but also the results can supply references to measure the pipe creep during the whole cycles of the operating period.
本文针对该问题的国内外研究现状，紧密结合工程建设的需要，应用CASTEM2000软件，对中国实验快堆的事故余热排放系统的热段钠管道进行了详细的数值模拟和研究，以探寻一种合适的研究中国实验快堆高温钠管道蠕变的分析方法。主要内容如下：
通过运用2002版RCC-MR《快中子增殖堆核岛机械设备设计和建造规则》标准和CASTEM2000计算程序，采用线弹性分析理论对中国实验快堆的事故余热排放系统的热段钠管道进行详细的应力分析与评定，包括管道强度计算，管道变形分析，管道支撑受力分析(静载荷分析)，以及在整个工作寿期内的总体应变和疲劳——蠕变分析。首次完成了对超过材料蠕变温度的高温钠管道的高温蠕变分析，为此段钠管道的安全运行提供了技术上的保证，同时其分析结果对日后快堆高温钠管道的蠕变应变测量和在役检查提供参考；并且本论文对RCC-MR规范的运用也对中国钠冷快中子增殖堆的高温管道设计标准的建立提供依据。
China Experimental Fast Reactor(CEFR) is under construction. There are many high temperature sodium pipes important to safety of CEFR, which they are have the hot temperature and long time of the thermal cycle in the total operating period. But this issue is one of the important technologic problem to effect the construction of CEFR. In order to ensure the safety of fast reactor, it is important and necessary to analyses to prevent the different kinds of damages, appraisal of progressive deformation, fatigue and creep assessment.
Upon the investigation on the domestic and foreign status of this issue, and according to the situation of CEFR, the detailed numerical analysis about high temperature sodium pipe of the accident excess heat discharging system can find out the way to research the high temperature creep of CEFR, and then the program of CASTEM2000 will be used to stress calculation. The major researches are outlined as the following:
The detailed stresses are calculated using the linear elastic beams method about high temperature sodium pipe of the accident excess heat discharging system. The mechanical calculations are based on those results and respect the rules of the RCC-MR Edition 2002, and then the program of CASTEM2000 is used to stress calculation. The pipe analysis is included which type of damage, reactions of supports (dynamic loading is not taken into account), negligible creep or significant creep and creep-fatigue calculation according to the segment of pipe's loading and boundary conditions during the total period. This segment of sodium pipe analysis can not only provide the safety of CEFR, but also the results can supply references to measure the pipe creep during the whole cycles of the operating period.
引文
[1] “中国实验快堆工程”，徐銤，CEFR内部文件，200 1．10。
[2] RCC-MR《快中子增殖堆核岛机械设备设计和建造规则》，2002版。
[3] RCC-MR附录“A3-16S”，2002版。
[4] CEFR01L01HYS07-JS《事故余热排放系统水力计算书》，叶原武。
[5] CEFR01L01HYS05-JS《事故余热排放系统管道应力分析报告》，梁兵兵，孙学伟，上海核工程研究设计院。
[6] CEFR01B05HES07-JS《二回路和事故余热排放系统部分管道的应力分析和接管力校核报告》，李笑天，清华大学核能与新能源技术研究院。
[7] CEFRZ08ZTS01《中国实验快堆运行工况》，马大园。
[8] CEFRZ24ZTS01《中国实验快堆初步安全分析报告》修改版。
[9] "the code RCC-MR rules for design and construction of fast breeder liquid metal cooled reactors" IAEA-SM-307/12, 1989
[10] 《PRESENTATION et UTILISATION de CASTEM2000 》E. Le Fichoux ENSTA-LME 1998. 4
[11] 《压力管道应力分析》唐永进著，中国石化出版社，2003．11
[12] 《钠冷快堆安全分析》张东辉，快堆运行人员培训教材，2002
[13] “高温蠕变分析的非线性连续损伤力学模型”荆建平等《推进技术》，200 1．4
[2] RCC-MR《快中子增殖堆核岛机械设备设计和建造规则》，2002版。
[3] RCC-MR附录“A3-16S”，2002版。
[4] CEFR01L01HYS07-JS《事故余热排放系统水力计算书》，叶原武。
[5] CEFR01L01HYS05-JS《事故余热排放系统管道应力分析报告》，梁兵兵，孙学伟，上海核工程研究设计院。
[6] CEFR01B05HES07-JS《二回路和事故余热排放系统部分管道的应力分析和接管力校核报告》，李笑天，清华大学核能与新能源技术研究院。
[7] CEFRZ08ZTS01《中国实验快堆运行工况》，马大园。
[8] CEFRZ24ZTS01《中国实验快堆初步安全分析报告》修改版。
[9] "the code RCC-MR rules for design and construction of fast breeder liquid metal cooled reactors" IAEA-SM-307/12, 1989
[10] 《PRESENTATION et UTILISATION de CASTEM2000 》E. Le Fichoux ENSTA-LME 1998. 4
[11] 《压力管道应力分析》唐永进著，中国石化出版社，2003．11
[12] 《钠冷快堆安全分析》张东辉，快堆运行人员培训教材，2002
[13] “高温蠕变分析的非线性连续损伤力学模型”荆建平等《推进技术》，200 1．4
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