乏燃料干式贮存设施临界计算研究

doi:10.11889/j.0253-3219.2016.hjs.39.070601

Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (7): 70601-070601.doi: 10.11889/j.0253-3219.2016.hjs.39.070601

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Calculation study on the criticality of dry storage facilities for spent fuel

HONG Zhe^1,2, ZHAO Shangui², ZHANG Min², ZHANG Liang², LIU Zhuo³

1 China Institute of Atomic Energy, Beijing 102413, China;
2 Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China;
3 Beijing Atom High Tech Co., Ltd., Beijing 102413, China

Received:2016-03-22 Revised:2016-04-01 Online:2016-07-10 Published:2016-07-08

Abstract

Abstract:

Background: 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: The aim is to study the criticality safety of spent fuel dry storage facility. Methods: 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: 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: It is possible to provide some proposals on the research of criticality safety.

Key words: Dry storage, Burnup credit, Criticality safety, Spent fuel

CLC Number:

TL249

HONG Zhe, ZHAO Shangui, ZHANG Min, ZHANG Liang, LIU Zhuo. Calculation study on the criticality of dry storage facilities for spent fuel[J].Nuclear Techniques, 2016, 39(7): 70601-070601.

References

1 http://www.nrc.gov/waste/spent-fuel-storage/diagram-typical-dry-cask-system.html[OL], 2015-4-13

2 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

3 Holtec international final safety analysis report for the HI-STORM 100 cask system[R]. Revision 9, USA:Nuclear Regulatory Commission, February 13, 2010

4 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

5 张普忠, 陈义学, 马续波, 等. 基于燃耗信任制的核电厂乏燃料贮存水池临界计算[J]. 核动力工程, 2010, 31(2):24-28 ZHANG Puzhong, CHEN Yixue, MA Xubo, et al. Criticality calculations of burnup-credit spent fuel storage pool for nuclear power plants[J]. Nuclear Power Engineering, 2010, 31(2):24-28

6 夏兆东, 周小平, 李晓波, 等. 田湾核电站乏燃料水池采用燃耗信任制的计算研究[J]. 原子能科学技术, 2013, 47(11):2098-2102 XIA Zhaodong, ZHOU Xiaoping, LI Xiaobo, et al. Calculation study of TNPS spent fuel pool using burnup credit[J]. Atomic Energy Science and Technology, 2013, 47(11):2098-2102

7 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

8 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[J]. 核工程研究与设计, 2004, 48:2-11 ZHOU Yaodong. Application and development of burnup credit in criticality safety design for PWR spent fuel storage pool[J]. Research and Design of Nuclear Engineering, 2004, 48:2-11

9 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

10 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

11 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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Calculation study on the criticality of dry storage facilities for spent fuel

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