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乏燃料干式贮存设施临界计算研究
Calculation study on the criticality of dry storage facilities for spent fuel
- 核技术 2016年39卷第7期 文章编号：070601
- 作者机构：
1.中国原子能科学研究院 北京 102413;
2.环境保护部核与辐射安全中心 北京 100082;
3.原子高科股份有限公司 北京 102413
- 作者简介：
[ "洪哲,男,1984年出生,2011年毕业于中国原子能科学研究院,研究领域为核燃料循环与材料", "HONG Zhe, male, born in1984, graduated from China Institute of Atomic Energy in 2011, focusing on nuclear fuel cycle and materials Corresponding author: LIU Zhuo, E-mail: liuzhuo0409117@126.com" ]
刘卓, E-mail:liuzhuo0409117@126.com LIU Zhuo, E-mail:liuzhuo0409117@126.com
- 基金信息：
DOI：10.11889/j.0253-3219.2016.hjs.39.070601
中图分类号： TL249收稿日期：2016-03-22，
修回日期：2016-04-01，
纸质出版日期：2016-07
- 稿件说明：
移动端阅览
洪哲, 赵善桂, 张敏, 等. 乏燃料干式贮存设施临界计算研究[J]. 核技术, 2016,39(7):070601
Zhe HONG, Shangui ZHAO, Min ZHANG, et al. Calculation study on the criticality of dry storage facilities for spent fuel[J]. Nuclear techniques, 2016, 39(7): 070601
洪哲, 赵善桂, 张敏, 等. 乏燃料干式贮存设施临界计算研究[J]. 核技术, 2016,39(7):070601 DOI： 10.11889/j.0253-3219.2016.hjs.39.070601.
Zhe HONG, Shangui ZHAO, Min ZHANG, et al. Calculation study on the criticality of dry storage facilities for spent fuel[J]. Nuclear techniques, 2016, 39(7): 070601 DOI： 10.11889/j.0253-3219.2016.hjs.39.070601.
摘要
以HI-STORM 100乏燃料干式贮存设施内部装载AFA-3G燃料组件为研究对象，用MCNP （Monte Carlo N Particle Transport Code） 4C程序，通过改变贮存设施内外的水密度，采用新燃料假设对不同工况下的临界安全进行研究。结果表明，在正常工况下，
k
eff
远低于0.93，是临界安全的。在事故工况下，当水密度大于0.8 g·cm
-3
时，存在临界安全问题。然后选取适当的核素，通过使用ORIGEN-ARP程序，得到不同燃耗下核素的组成，在同一模型下考虑燃耗信任制，对干式贮存设施的临界安全进行研究。在此基础上，给出了乏燃料干式贮存设施临界安全工作的相关建议。
Abstract
Background:
2
The plight of a large number of spent fuel accumulation can be effectively alleviated by constructing spent fuel dry storage facilities. Having been widely adopted in foreign countries
spent fuel dry storage technology has not yet been studied in our country.
Purpose:
2
The aim is to study the criticality safety of spent fuel dry storage facility.
Methods:
2
The research object is HI-STORM 100 spent fuel dry storage facility internal loading AFA-3G fuel assembly in this paper. Using the MCNP (Monte Carlo N Particle Transport Code) 4C code
criticality safety was studied by changing the density of the water inside and outside of the storage facilities.
Results:
2
The results indicate that
k
eff
is far below 0.93 in the normal condition
which is safety. But there would be some problems if the water density is greater than 0.8 g·cm
-3
under accident condition. Nuclides composition based on burnup credit can be got by using ORIGEN-ARP code. And then calculation study on the critical safety of dry storage facilities in the same model was carried out.
Conclusion:
2
It is possible to provide some pro
posals on the research of criticality safety.
关键词
Keywords
references
http://www.nrc.gov/waste/spent-fuel-storage/diagram-typical-dry-cask-system.html http://www.nrc.gov/waste/spent-fuel-storage/diagram-typical-dry-cask-system.html [OL], 2015-4-13
Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB). Joint convention on the safety of spent fuel management and on the safety of radioactive waste management[C]. Report of the Federal Republic of Germany for the 15th Review Meeting, Vienna, May 2015
Holtec international final safety analysis report for the HI-STORM 100 cask system[R]. Revision 9, USA:Nuclear Regulatory Commission, February 13, 2010
Gauld I C, Bowman S M, Horwedel J E. Origen-ARP:automatic rapid processing for spent fuel depletion, decay, and source term analysis[R]. USA:ORNL, 2011
张 普忠 , 陈 义学 , 马 续波 , . 基于燃耗信任制的核电厂乏燃料贮存水池临界计算 . 核动力工程 , 2010 . 31 ( 2 ): 24 - 28 .
Puzhong ZHANG , Yixue CHEN , Xubo MA , . Criticality calculations of burnup-credit spent fuel storage pool for nuclear power plants . Nuclear Power Engineering , 2010 . 31 ( 2 ): 24 - 28 .
夏 兆东 , 周 小平 , 李 晓波 , . 田湾核电站乏燃料水池采用燃耗信任制的计算研究 . 原子能科学技术 , 2013 . 47 ( 11 ): 2098 - 2102 .
Zhaodong XIA , Xiaoping ZHOU , Xiaobo LI , . Calculation study of TNPS spent fuel pool using burnup credit . Atomic Energy Science and Technology , 2013 . 47 ( 11 ): 2098 - 2102 .
攸国顺. 燃耗信任制技术在压水堆乏燃料贮存水池中应用的研究[D]. 北京:中国原子能科学研究院, 2005.
YOU Guoshun. Study on the application of burnup credit in pressurized water reactor storage pool of spent fuel[D]. Beijing:China Institute of Atomic Energy, 2005
周 耀栋 . 燃耗信任在PWR乏燃料贮存水池临界安全设计中的应用和发展综述 . 核工程研究与设计 , 2004 . 48 2 - 11 .
Yaodong ZHOU . Application and development of burnup credit in criticality safety design for PWR spent fuel storage pool . Research and Design of Nuclear Engineering , 2004 . 48 2 - 11 .
Burnup credit in the criticality safety analyses of PWR spent fuel in transportation and storage casks[R]. Division of Spent Fuel Storage and Transportation, Interim Staff Guidance-8, Revision 3, USA:Nuclear Regulatory Commission
Radulescu G, Gauld I C, Ilas G, et al. An approach for validating actinide and fission product burnup credit criticality safety analyses-isotopic composition predictions[R]. NUREG/CR-7108 (ORNL/TM-2011/509), USA:Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2012
Mueller D E, Scaglione J M, Wagner J C, et al. An approach for validating actinide and fission product burnup credit criticality safety analyses-criticality ( k eff ) predictions[R]. NUREG/CR-7109 (ORNL/TM-2011/514), USA:Nuclear Regulatory Commission, Oak Ridge National Laboratory, April 2012
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