期刊文献+

缓发超临界过程燃料元件温度场动态分析与快速计算

Dynamic Analysis and Fast Calculation of Fuel Element Temperature Field During Delayed Supercritical Process
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摘要 针对反应堆缓发超临界过程特点,本工作建立了物理、热工及热量传递模型,采用准稳态方法对缓发超临界过程反应堆平均通道单根燃料元件温度场进行了计算分析,并与某反应堆仿真平台计算结果进行对比。分析表明,在功率变化不剧烈的反应堆动态过程,采用准稳态计算方法可以较准确地计算出燃料元件温度场随时间的变化规律。且本工作模型相对简单,计算速度快,对于反应堆动态运行研究及船用反应堆事故分析均有重要意义,对于反应堆热工设计也具有重要的参考价值。 Based on the characters of the reactor in the delayed supercritical process, the physical and thermal and heat transmission model were founded, and the quasi-static method was employed. The temperature field of a single fuel element in the average channel of the reactor during the delayed supercritical process was calculated and analyzed, and the results were compared with those got from the simulation platform of the same reactor. It is shown that in the slow dynamic process, the fuel element temperature field could also be calculated exactly by the quasi-static method. Besides, the model in the paper is relatively simple and has fast calculation velocity, which is of great importance to the reactor’s dynamic analysis and some accident analysis. It is also useful to the reactor’s thermal design.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2010年第B09期312-316,共5页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(10575131)
关键词 燃料元件 温度场 快速计算 中子动力学 准稳态方法 fuel element, temperature field fast calculation neutron kinetics, quasi-staticmethod
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  • 1陈文振,朱波,黎浩峰.小阶跃反应性输入时点堆中子动力学方程的解析解[J].物理学报,2004,53(8):2486-2489. 被引量:10
  • 2张帆,陈文振,蔡章生.临界反应堆阶跃正反应性输入时中子密度响应的近似修正解[J].原子能科学技术,2006,40(B09):5-8. 被引量:7
  • 3LAWRENCE R D, DORNING J J. Smoothing and extrapolation techniques for reactor kinetics [J]. Nuclear Science and Engineering, 1977, 64 492-507.
  • 4ABOANBER A E, HAMADA Y M. PWS: An efficient code system for solving space independent nuclear reactor dynamics[J]. Annals of Nuclear Energy, 2002, 29:2 159-2 172.
  • 5KUENG Y. Polynomial approach to reactor ki netics equations[J]. Nuclear Technology and En gineering, 1978, 66: 235-242.
  • 6CHEN Wenzhen, KUANG Bo, GUO Lifeng, et al. New analysis of prompt supercritical process with temperature feedback [J]. Nuclear Engineering and Design, 2006, 236: 1 326-1 329.
  • 7张帆.潜艇核反应堆碘坑内启动研究[D].武汉:海军工程大学,2004.
  • 8蔡章生.反应性事故中的瞬发加热效应.核动力工程,1994,67(2):58-63.
  • 9刘旭东.TPFAP-E程序使用说明[R].北京:核工业核电软件中心,1992..
  • 10于雷.船用反应堆三维细网燃料计算研究[R].武汉:海军工程大学,2000..

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