快堆保护系统与数字化浅析
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- 英文论文题名：Brief analysis of structure and logic of fast reactor protection system
- 论文作者：盛静 ; 陈树明
- 英文论文作者：SHENG Jing ; CHEN Shu-ming ; Department of CEFR Project ; China Institute of Atomic Energy
- 年：2015
- 作者机构：中国原子能科学研究院快堆研究设计所;
- 论文关键词：反应堆保护系统 ; 快中子反应堆 ; 数字化反应堆保护系统 ; 结构 ; 逻辑
- 英文论文关键词：reactor protection system ; SFR ; digital RPS ; dtructure ; logic
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第2册（核能动力分卷（上））
- 语种：中文
- 分类号：TL433
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：5
- 文件大小：262k
- 原文格式：O
- 会议级别：全国
摘要
在核电站的设计和运行中,安全是至关重要的。反应堆保护系统的主要功能是保证安全停堆以及防止放射性材料的释放。为了防止无保护瞬态事故威胁到快堆安全,我们需要一个高度可靠的反应堆保护系统。数字化仪控系统与模拟仪控系统相比,其经济效益和可用性都要更高,但在软件可靠性和共因失效上引进了新的问题,且缺乏有效的V&V方法,即使如此其发展依然势不可挡。本文概述了一些国际上典型的快中子反应堆的保护系统,简述其结构和逻辑,同时就数字化反应堆保护系统的应用现状和优缺点,阐述了其发展可能遇到的困难,认为在软件完全取代硬件前,使用FPGA的专用集成电路技术已经是目前最为适用且普遍接受的方案,讨论了这一方案中如何消减软件带来的共因失效,并就反应堆保护系统完全数字化之后可能出现的问题提出了一些预测分析和建议。
Safety is one of the most important concerns in the design and operation of NPPs.The main function of a Reactor Protection System(RPS)is to safely shutdown the reactor and prevents the release of radioactive materials.To defend the unprotected transient accidents which can significantly challenge Sodium Fast Reactors(SFRs),a highly reliable RPS is required.This paper summarizes some RPSs of internationally representative SFRs.It also lists the prospects and difficulties of digital RPS development and proposes some forecasts and recommendations as well.
Safety is one of the most important concerns in the design and operation of NPPs.The main function of a Reactor Protection System(RPS)is to safely shutdown the reactor and prevents the release of radioactive materials.To defend the unprotected transient accidents which can significantly challenge Sodium Fast Reactors(SFRs),a highly reliable RPS is required.This paper summarizes some RPSs of internationally representative SFRs.It also lists the prospects and difficulties of digital RPS development and proposes some forecasts and recommendations as well.
引文
[1]Jacob D.DeWitte,Reactor Protection System Design Alternatives for Sodium Fast Reactors[D].MASSACHUSETTS INSTITUED OF TECHNOLOGY,JANUARY 28,2011:40-43.
[2]Dong-Young Lee,Jong-Gyun Choi,and Joon Lyou.A Safety Assessment Methodology for a Digital Reactor Protection System[J].A International Journal of Control,Automation,and Systems,vol.4,no.1,February 2006:105-112.
[3]Jong Gyun Choi,Dong Young Lee.Development of RPS Trip Logic Based on PLD Technology[J].Nuclear Engineering and Technology,VOL.44 NO.6 AUGUST 2012:697-708.
[4]宋维.《中国实验快堆保护系统可靠性评价》,[J].核科学与工程,2012.6.
[5]M.Sivaramakrishna,Manish Kumar.Design of Advanced Integrated Reactor Protection System for Commercial Fast Breeder Reactor[J].Engineering Management Research;Vol.l,No.2;2012:82-84.
[6]C.Senthil Kumar,A.John Arul,Om Pal Singh,K.Suryaprakasa Rao.Reliability analysis of shutdown system[J].Annals of Nucl ear Energy 32,2005:63-87.
[7]Sacit M.Cetiner,Daniel G.Cole,David L.Fugate,Roger A.Kisner,Michael A.Kristufek,Alexander M.Melin,Michael D.Muhlheim,Nageswara S.Rao and Richard T.Wood.Definition of Architectural Structure for Supervisory Control System of Advanced Small Modular Reactors[J].ORNL/TM-2013/320,SMR/ICHMI/ORNL/TR-2013/04:40-41,100-101.
[8]R.W.Hardy,G.L.Stimmell.APPENDIX G,AMENDMENT 13 TO THE PRISM(ALMR)-Preliminary Safety Information Document[R].GEFR-00793,UC-87TA,MAY 1990.
[9]Seung-Hwan SEONG,Dong-Hoon Kim,Kwang-Seop Son,Gwi-Sook Jang,Kwang-Il Jeong and Jong-Yong Keum.Preliminary Study on Architecture of Reactor Protection System for Prototype SFR[R].Transactions of the Korean Nuclear Society Autumn Meeting,Gyeongju,Korea,October 25-26,2012.
[10]肖鹏,周继翔,刘宏春.反应堆保护系统结构与可靠性的关系[J].核动力工程,2013.7:179-183.
[11]Westinghouse Technology Systems Manual[R].Section 12.1 Reactor Protection System.
[12]冯伟伟.安全级仪控系统平台选型调研报告[R].中国原子能科学研究院快堆研究设计所,2015.1.
[2]Dong-Young Lee,Jong-Gyun Choi,and Joon Lyou.A Safety Assessment Methodology for a Digital Reactor Protection System[J].A International Journal of Control,Automation,and Systems,vol.4,no.1,February 2006:105-112.
[3]Jong Gyun Choi,Dong Young Lee.Development of RPS Trip Logic Based on PLD Technology[J].Nuclear Engineering and Technology,VOL.44 NO.6 AUGUST 2012:697-708.
[4]宋维.《中国实验快堆保护系统可靠性评价》,[J].核科学与工程,2012.6.
[5]M.Sivaramakrishna,Manish Kumar.Design of Advanced Integrated Reactor Protection System for Commercial Fast Breeder Reactor[J].Engineering Management Research;Vol.l,No.2;2012:82-84.
[6]C.Senthil Kumar,A.John Arul,Om Pal Singh,K.Suryaprakasa Rao.Reliability analysis of shutdown system[J].Annals of Nucl ear Energy 32,2005:63-87.
[7]Sacit M.Cetiner,Daniel G.Cole,David L.Fugate,Roger A.Kisner,Michael A.Kristufek,Alexander M.Melin,Michael D.Muhlheim,Nageswara S.Rao and Richard T.Wood.Definition of Architectural Structure for Supervisory Control System of Advanced Small Modular Reactors[J].ORNL/TM-2013/320,SMR/ICHMI/ORNL/TR-2013/04:40-41,100-101.
[8]R.W.Hardy,G.L.Stimmell.APPENDIX G,AMENDMENT 13 TO THE PRISM(ALMR)-Preliminary Safety Information Document[R].GEFR-00793,UC-87TA,MAY 1990.
[9]Seung-Hwan SEONG,Dong-Hoon Kim,Kwang-Seop Son,Gwi-Sook Jang,Kwang-Il Jeong and Jong-Yong Keum.Preliminary Study on Architecture of Reactor Protection System for Prototype SFR[R].Transactions of the Korean Nuclear Society Autumn Meeting,Gyeongju,Korea,October 25-26,2012.
[10]肖鹏,周继翔,刘宏春.反应堆保护系统结构与可靠性的关系[J].核动力工程,2013.7:179-183.
[11]Westinghouse Technology Systems Manual[R].Section 12.1 Reactor Protection System.
[12]冯伟伟.安全级仪控系统平台选型调研报告[R].中国原子能科学研究院快堆研究设计所,2015.1.