期刊文献+

板状燃料元件流道堵塞事故预防与探测技术研究 被引量:4

Research on prevention and detection technology of flow channel blockage accident of plate-type fuel elements
下载PDF
导出
摘要 板状燃料元件用于研究堆中表现出良好的辐照性能。通过对国内外一些使用板状燃料元件研究堆堵流事故实例的调研,发现板状燃料元件板间的栅距通常很小,堆芯冷却剂流道狭窄,堵流事故的发生大都由异物进入流道或燃料肿胀引起。选取中国先进研究堆(China Advanced Research Reactor,CARR)作为特征研究对象,采用RELAP5/MOD3.2热工计算程序,对CARR堆芯、堆本体、单盒组件、堆外冷却回路等进行了热工水力模拟计算,结果表明:当反应堆功率提升时,堵塞的流道内燃料组件温度上升,冷却剂开始发生沸腾,功率会发生明显波动。通过中子注量率与功率的监控以及燃料温度的分析,有助于及早探知和预防堵流事故的进一步发展扩大。 [Background]Plate-type fuel element exhibits excellent irradiation properties in research reactor while the grid spacing between the fuel element plates is usually very small.Most of the blockage accidents are caused by foreign matters entering the flow channel or fuel swelling due to the narrow coolant flow channel in the core.[Purpose]This study aims to analyze the process of blockage accidents,and put forward effective preventive measurements and detection methods.[Methods]Based on the investigation of some typical accidents abroad,China advanced research reactor(CARR)was taken as a feature research object,and the thermal hydraulic simulation calculation of CARR core,reactor body,single fuel assembly and cooling circuit outside the reactor was carried out by using the RELAP5/MOD3.2 thermal calculation program.Modeling and analysis of the specific flow channel blockage accident process on CARR was finished.[Results]Simulation results show that the temperature of the fuel assembly in the blocked flow passage will increase when the reactor power is raising,then the coolant will begin to boil,and the power will fluctuate significantly.[Conclusions]It is necessary to strictly control the quality of core operation.The monitoring of neutron flux rate and reactor power,and analyzing fuel temperature are helpful to detect and prevent the further development of the blockage accident.
作者 丁丽 骆贝贝 花晓 宁波 乔雅馨 DING Li;LUO Beibei;HUA Xiao;NING Bo;QIAO Yaxin(China Institute of Atomic Energy,Beijing 102413,China)
出处 《核技术》 CAS CSCD 北大核心 2020年第4期7-13,共7页 Nuclear Techniques
基金 民用核设施安全监督管理技术支持专项资助。
关键词 板状燃料元件 堵流事故 中国先进研究堆 Plate-type fuel element Flow channel blockage accident China Advanced Research Reactor
  • 相关文献

参考文献3

二级参考文献13

  • 1陈彭,王华荣,张培生.压水堆堆内试验仪表化燃料元件初始温度分布计算程序[J].原子能科学技术,2003,37(z1):157-160. 被引量:1
  • 2[1]Sims TM, Tabor WH. Report on Fuel-plate Mel-ting at the Oak Ridge Research Reactor: ORNL-TM-627[R]. USA, Oak Ridge: ORNL, 1964.
  • 3[2]RETRAN-02程序员手册[Z].北京:核工业部核电软件中心,1987.
  • 4[3]神永雅纪.JRR-3ツリサイド燃料炉心の炉心定常热水力解析及び炉心流路闭塞事故解析:JAERI-Tech-97-015[R].日本:日本原子力研究所,1997.
  • 5[4]神永雅纪,山本喜和,渡边终吉.JRR-4ツリサイド燃料炉心の炉心定常热水力解析及び炉心流路闭塞事故解析:JAERI-Tech-96-039[R].日本:日本原子力研究所,1996.
  • 6李小川. 燃料组件泄漏问题[R]. 广东:大亚湾核电站,1996.Li Xiaochuan. The Problems of Fuel Assembly Leakage[R]. Guangdong: Daya Bay Nuclear Power Plant, 1996(in Chinese).
  • 7唐纳德·奥兰德.核反应堆燃料元件基本问题[M]. 李恒德,潘金生,柳百新, 等译. 北京:原子能出版社, 1983.428~438.Olander DR. Fundamental Aspects of Nuclear Reactor Fuel Elements[M]. Li Hende, Pan Jinsheng, Liu Baixin, et al. Beijing:Atomic Energy Press, 1983. 428~438(in Chinese).
  • 8Marcin SZUTA. Defect Trap Model of Fission Gas Behavior in UO2 Fuel During Irradiation [R]. Otwock-Swierk: Institute of Atomic Energy, 2003.
  • 9Leuthro C, Brissaud A, Missud J P, et al. Relation ships Between the Characteristics of Cladding Defects and the Activity of the Primary Coolant Circuit, An Aid for the Management of Leaking Fuel Assemblies in PWR [C]. Proc of the 1991 International Topical Meeting on Light Water Reactor Fuel Performance, Avignon, France, April, 21 - 24, 1991.
  • 10Beraha R. Fuel Survey in the Light Water Reactors based on the Activity of the Fission Products[J]. Nuclear Technology, 1980, 49:426 - 434.

共引文献45

同被引文献15

引证文献4

二级引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部