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空间核反应堆安全分析 被引量:9

Safety Analysis of Space Nuclear Reactor
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摘要 空间核反应堆是空间能源的重要候选方案,其寿命长、功率大、结构紧凑,但其特有的中子学特性、与传统快堆迥异的设计方案对堆芯安全分析提出了挑战。本文以热管型空间堆为例,首先基于蒙特卡洛方法对空间堆在水淹和沙埋事故工况下,进行了稳态中子学计算分析,结果表明:堆芯在事故工况下不会重返临界。同时,基于瞬态多物理分析程序TMACS,进行了单根控制鼓旋转瞬态过程计算。结果表明:空间堆在热工反馈和热膨胀反馈的多物理耦合下,在特定的瞬态过程中能够保持功率稳定,满足安全要求。 Space nuclear reactor is an important candidate for space power source.It has the advantages such as long life,large power,and compact structure.However,its unique characteristics of neutronics and the design scheme different from traditional fast nuclear reactors pose challenges to the core safety analysis.In this paper,the calculation and analysis of the steady-state neutronics of a heat-pipe space reactor under the accident conditions of water flooding and sand burial are conducted based on the Monte-Carlo method.The results show that the core would not return to the critical state under the accident conditions.Meanwhile,based on the transient multi-physics analysis program TMACS,the transient rotation process of a single control drum is carried out.The results show that,in a particular transient process under the multiple physical couplings of thermal-hydraulic feedback and thermal expansion feedback,the space reactor can maintain the power stable and meet the safety requirement.
作者 张一帆 屈伸 曹良志 郑友琦 ZHANG Yifan;QU Shen;CAO Liangzhi;ZHENG Youqi(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,Shaanxi,China)
出处 《上海航天》 CSCD 2019年第6期121-125,共5页 Aerospace Shanghai
关键词 空间堆 安全分析 瞬态计算 多物理耦合 space reactor safety analysis transient calculation multi-physical coupling
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  • 1张光玉,张红,涂善东,庄骏.热管在核电工程中的应用[J].原子能科学技术,1997,31(1):89-96. 被引量:10
  • 2HEHR B, HAWARI A. Calculation of the ther- mal neutron scattering cross sections of alpha quartz[C] // Proceedings of International Confer- ence on the Physics of Reactors, Nuclear Power..A Sustainable Resource. Interlaken, Switzer- land= [s. n.], 2008.
  • 3McCONN R J, GESH C J, PAGH R T, et al. Compendium of material composition data for ra diation transport modeling, PNNL 99352 [R]. Washington: Pacific Northwest National Labora- tory, 2011.
  • 4EL-GENK M S, TOURNIER J M. Conceptual design of HP-STMCs space reactor power system for 110 kWe, 10-year missions[C]//Proceedings of the Space Technology and Applications Inter national Forum (STAIF-2004). Melville: Ameri- can Institute of Physics, 2004.
  • 5GLOUCHKOV E S, PONOMAREV STEPNOI N N. Intermediate heterogeous assembly with highly enriched uranium dioxide and sand/water radial reflector, HEU-COMP-MIXED-004 [DB/ OL]. http://www, oecd-nea, org/science/wpncs/ icsbep/.
  • 6GLASSTONE S, BELL G. Nuclear reactor theo- ryEM:. New York: Van Nostrand Reinhold Company, 1970: 401-406.
  • 7MacFARLANE R E. New thermal neutron scat tering files for ENDF/B-Vl, release 2, LA 12639-MS[R]. US: LANL, 1994.
  • 8CHADWICK M B, HERMAN M, OBLOZINSK Y P, et al. ENDF/B-:. 1, Nuclear data for sci enee and technology: Cross sections, covariance, fission product yields and decay data[J]. Nuclear Data Sheets, 2011, 112(12).. 2 887-2 996.
  • 9JUDITH F B. MCNP: A general Monte Carlo N- particle transport code, version 4B, LA-12625-M [R]. US: LANL, 1997.
  • 10EI-Genk, M.S. and Tournier, J:M. , "Conceptual Design of HP-STMCs Space Reactor Power System for 110 kWe, 10-Year Missions [C]. Proceedings of the Space Technology and Applications International Forum (STAIF-2004), edited by M.S. EI-Genk, American Institute of Physics, Melville, NY, 2004a.

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