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Analysis on natural circulation capacity of the CARR

Analysis on natural circulation capacity of the CARR
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摘要 The investigation on natural circulation (NC) characteristics of the China Advanced Research Reac- tor(CARR) is very valuable for practical engineering application and also a key subject for the CARR. In this study, a computer code was developed to calculate the NC capacity of the CARR under different pool water temperatures. Ef- fects of the pool water temperature on NC characteristics were analyzed. The results show that with increasing pool water temperature, the NC flow rate increases while the NC capacity decreases. Based on the computation results and theoretical deduction, a correlation was proposed on predicting the relationship between the NC mass flow and the core power under different conditions. The correlation prediction agrees well with the computational result within ±10% for the maximal deviation. This work is instructive for the actual operation of the CARR. The investigation on natural circulation (NC) characteristics of the China Advanced Research Reactor(CARR) is very valuable for practical engineering application and also a key subject for the CARR. In this study, a computer code was developed to calculate the NC capacity of the CARR under different pool water temperatures. Effects of the pool water temperature on NC characteristics were analyzed. The results show that with increasing pool water temperature, the NC flow rate increases while the NC capacity decreases. Based on the computation results and theoretical deduction, a correlation was proposed on predicting the relationship between the NC mass flow and the core power under different conditions. The correlation prediction agrees well with the computational result within ±10% for the maximal deviation. This work is instructive for the actual operation of the CARR.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第3期186-192,共7页 核技术(英文)
关键词 反应堆 循环容量 计算机 编码 China Advanced Research Reactor, Natural circulation capacity, Steady state characteristics
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参考文献9

  • 1Ishii M, Kataoka I. Nuclear Engineering and Design, 1984, 81:411-425.
  • 2Zvirin Y, Duffey C W, Duffey R B. Experimental and analytical investigation of a PWR natural circulation loop.1980, NP-1364-SR.
  • 3Kim M J, Lee Y B. International Journal on Heat Mass Transfer, 2001, 44: 389-397.
  • 4Misale M, Frogheri M. International Comm. Heat Mass Transfer, 1999, 26(5): 597-606.
  • 5Ramsom V H. RELAP/MOD2 Code Manual, Vol. 1, Code structure, systems models, and solution method. 1985,NUREG/CR-4312, EGG-2396, EG & G Idaho Inc..
  • 6Jiang S Y. Kerntechnik, 1998, 63: 132-138.
  • 7Yang Z M, Huang Y P, Wang F, et al. Nuclear Power Engineering, 1999, 20: 219-222.
  • 8Sudo Y, Kaminaga M. Transaction of ASME, Journal of Heat Transfer, 1987, 6(4): 415-426.
  • 9Kanminaga M. JAERI-M, 1990, 90(21): 2201-2213.

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