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1.中国核动力研究设计院 核反应堆系统设计技术重点实验室 成都 610213
2.中国核动力研究设计院 成都 610213
[ "刘余, 男, 1983年出生, 2010年于清华大学获博士学位, 主要从事反应堆热工水力和安全分析研究", "LIU Yu, male, born in 1983, graduated from Qsinghua University with a doctoral degree in 2010, focusing on reactor thermal hydraulic and safety analysis" ]
收稿日期:2017-02-13,
修回日期:2017-03-02,
纸质出版日期:2017-05-10
移动端阅览
刘余, 任春明, 汤琪芬, 等. 核电厂运行瞬态分析软件PANTO的研发[J]. 核技术, 2017,40(5):050604
Yu LIU, Chunming REN, Qifen TANG, et al. Development of operational transient analysis code PANTO for nuclear power plant[J]. Nuclear techniques, 2017, 40(5): 050604
刘余, 任春明, 汤琪芬, 等. 核电厂运行瞬态分析软件PANTO的研发[J]. 核技术, 2017,40(5):050604 DOI: 10.11889/j.0253-3219.2017.hjs.40.050604.
Yu LIU, Chunming REN, Qifen TANG, et al. Development of operational transient analysis code PANTO for nuclear power plant[J]. Nuclear techniques, 2017, 40(5): 050604 DOI: 10.11889/j.0253-3219.2017.hjs.40.050604.
针对核电厂运行瞬态分析的功能需求,中国核动力研究设计院研发了PANTO(Program for Analysis ofNormal Transient and Overpressure)软件。该软件基于成熟可靠的系统分析模型和特殊部件模型,采用模块化的软件设计理念,应用面向对象的C++语言和java语言,具有完全自主知识产权。PANTO软件通过了单元测试、集成测试和系统测试,基本消除了所有的代码缺陷。针对秦山二期核电厂阶跃负荷增大10%与额定功率下全部甩负荷瞬态试验进行了验证计算。结果表明,PANTO软件能够较好地模拟瞬态中关键参数的变化情况,计算精度满足工程应用要求,适用于压水堆核电厂运行瞬态分析。
Background
2
The operational transient of a nuclear power plant mainly refers to transients or events that occur frequently or periodically during commissioning or power operation. The transient process involves the response of primary loop
secondary loop and the control system. Usually
particular software is used for transient analysis. Purpose:This study aims to develop the program for analysis of normal transient and overpressure (PANTO) software that fulfils the requirements of operational transient analysis.
Methods
2
Based on the mature and reliable system analysis model and special component model
object-oriented C++ language and java language were applied to design the modular software with completely independent intellectual property rights for PANTO. Through the unit testing
integration testing and system testing
all detected code defects were eliminated. Validation calculations were carried out for the 10% load step increase and complete load ejection at full power transient test which performed in the Qinshan Phase Ⅱ nuclear power plant.
Results
2
The results show that the PANTO can simulate the key parameters variation in the transients
and the calculation accuracy can meet the requirements of the engineering application.
Conclusion
2
The PANTO is applicable for operational transient analysis of PWR nuclear power plant.
张 英 , 陈 智 , 周 祖鉴 , . 用于核电厂数字化仪表控制系统优化设计的CATIA2程序的改进 . 核动力工程 , 2008 . 29 ( 1 ): 19 - 23 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200801004.htm .
Ying ZHANG , Zhi CHEN , Zujian ZHOU , . Improvement of CATIA2 code used in optimization design for digital instrument and control system of NPP . Nuclear Power Engineering , 2008 . 29 ( 1 ): 19 - 23 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200801004.htm .
刘 立欣 , 郑 利民 , 周 全福 . AP1000核电厂典型的运行瞬态分析 . 核技术 , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .
Lixin LIU , Limin ZHENG , Quanfu ZHOU . Preliminary study on operational transient analysis for AP1000 . Nuclear Techniques , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .
中国核动力院. 中核集团召开核电软件自主化项目启动会[EB/OL]. 2011-03-11[2016-05-13] . http://www.cnnc.com.cn/publish/portal0/tab426/info52484.htm http://www.cnnc.com.cn/publish/portal0/tab426/info52484.htm .
Nuclear Power Institute of China. CNNC held the kick-off meeting of self-reliance nuclear power plant design software project[EB/OL]. 2011-03-11[2016-05-13] . http://www.cnnc.com.cn/publish/portal0/tab426/info52484.htm http://www.cnnc.com.cn/publish/portal0/tab426/info52484.htm .
谢 仲生 . 核反应堆物理分析 , : 北京 原子能出版社 , 1980 . 310 - 311 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .
Zhongsheng XIE . Nuclear reactor physics analysis , : Beijing Atomic Energy Press , 1981 . 310 - 311 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .
朱 继洲 . 核反应堆安全分析 , : 西安 西安交通大学出版社 , 2004 . 42 - 43 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .
Jizhou ZHU . Nuclear reactor safety analysis , : Xi'an Xi'an Jiaotong University Press , 2004 . 42 - 43 . http://www.cnki.com.cn/Article/CJFDTOTAL-SYQY201603027.htm .
M A Abdallah , H M Ahmed , A R Mohammad . Pressurizer transients dynamic model . Nuclear Engineering and Design , 1982 . 73 ( 3 ): 447 - 453 . DOI: 10.1016/0029-5493(82)90018-8 http://doi.org/10.1016/0029-5493(82)90018-8 .
张 森如 , 王 建渝 . 核电厂控制调节系统在运行瞬态分析中的数值计算 . 核科学与工程 , 1988 . 8 ( 4 ): 324 - 329 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY198804005.htm .
Senru ZHANG , Jianyu WANG . Digital calculation of control and adjustment system in operational transient analysis for nuclear power plant . Chinese Journal of Nuclear Science and Engineering , 1988 . 8 ( 4 ): 324 - 329 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY198804005.htm .
李 经纬 . 秦山核电二期工程反应堆热工水力设计 . 核动力工程 , 1999 . 20 ( 4 ): 308 - 312 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG904.004.htm .
Jingwei LI . Reactor thermal hydraulic design for Qinshan Phase Ⅱ nuclear power project . Nuclear Power Engineering , 1999 . 20 ( 4 ): 308 - 312 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG904.004.htm .
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