中国实验快堆一回路热工水力稳态计算程序开发
Development of Thermal-Hydraulic Steady-State Analysis Program for Primary Loop of China Experimental Fast Reactor
-
摘要: 针对中国实验快堆(CEFR)的具体结构和稳态运行特点，利用Fortran语言开发了CEFR一回路热工水力稳态计算程序。重点开发了有关钠的多种物性的子程序、适应不同工况的钠的流动与换热计算子程序，并对关系式进行了对比分析，最后建立了稳态计算模型并开发了程序。在此基础上，对CEFR的一回路系统在满功率下的稳态热工水力特性进行了计算分析，所获得的结果同设计参数吻合，证明了所开发的子程序及稳态程序的正确性。Abstract: According to the characteristics of structure and steady-state for primary loop of China Experimental Fast Reactor (CEFR), a thermal-hydraulic steady-state analysis program was developed by using Fortran language. This paper focused on the development of a set of subroutine of physical properties of sodium and the sodium flow and heat transfer correlations for different operation conditions. And the difference among these correlations was compared. The calculation program was developed based on the steady model. At last, the thermal-hydraulic characteristics of steady-state of the primary loop of CEFR at full power were calculated. The calculation results are consistent with the design parameters and the correctness of the developed subroutines and steady-state calculation program was proved.
-
-
[1] MOCHIZUKI H, TAKANO M. Heat transfer in heat exchangers of sodium cooled fast reactor systems [J]. Nuclear Engineering and Design, 2009, 239: 295-307. [2] 邱仁森. 钠技术和液金属钠回路[M]. 北京：科学出版社，1987：83-104. [3] 石双凯，张振灿，张永积，等. 液态金属钠在圆管和套管内的传热实验研究[J]. 工程热物理学报，1981，2(2)：173-179.SHI Shuangkai, ZHANG Zhencan, ZHANG Yongji, et al. Experimental study of heat transfer to liquid metal sodium flowing in circular tube and annuli[J]. Journal of Engineering Thermophysics, 1981, 2(2): 173-179(in Chinese). [4] 丁振鑫. 快堆燃料组件水力特性计算[J]. 原子能科学技术，1991，25(5)：25-30.DING Zhenxin. The calculation of the hydraulic characteristics of FFR’s fuel assembly[J]. Atomic Energy Science and Technology, 1991, 25(5): 25-30(in Chinese). [5] 刘一哲，喻宏. 快堆燃料组件热工流体力学计算研究[J]. 原子能科学技术，2008，42(2)：128-134.LIU Yizhe，YU Hong. Thermal-hydraulic analysis of fuel subassemblies for sodium-cooled fast reactor[J]. Atomic Energy Science and Technology, 2008, 42(2): 128-134(in Chinese). [6] 徐銤. 快堆和我国核能的可持续发展[J]. 现代电力，2006，10(5)：76-81.XU Mi. Fast reactor and sustainable development of China nuclear energy[J]. Modern Electric Power, 2006, 10(5): 76-81(in Chinese). [7] 单建强，秋穗正，朱继洲，等. 安全分析用钠物性偏导数公式的推导研究[J]. 核动力工程，1997，6(3)：238-239.SHAN Jianqiang, QIU Suizheng, ZHU Jizhou, et al. Calculation of partial derivatives of thermophysical properties of sodium for safety analysis[J]. Nuclear Power Engineering, 1997, 6(3): 238-239(in Chinese). [8] 郝老迷. 快堆燃料组件的子通道分析[J]. 原子能科学技术，1993，27(5)：426-431.HAO Laomi. Subchannel analysis of fuel assembly for fast reactor[J]. Atomic Energy Science and Technology, 1993, 27(5): 426-431(in Chinese). [9] 张贵勤，向明忠，周学智. 液态金属钠在环管进口段的紊流换热实验研究[J].化工学报，1990（3）：346-351.ZHANG Guiqin, XIANG Mingzhong, ZHOU Xuezhi. Experimental investigation of turbulent heat transfer to liquid sodium in the thermal entrance region of an annulus[J]. CIESC Journal, 1990（3）: 346-351(in Chinese). [10] JAMAL M S. 流体流动手册[M]. 邓敦夏，译. 北京：中国石化出版社，2004. [11] 杨世铭，陶文铨. 传热学[M]. 北京：高等教育出版社，2006.
计量
- 文章访问数: 762
- HTML全文浏览量: 2
- PDF下载量: 1248
下载:
