Analysis on natural circulation capacity of the CARR

Analysis on natural circulation capacity of the CARR 1 corresp first-author E-mail: wxtian@mailst.xjtu.edu.cn E-mail: wxtian@mailst.xjtu.edu.cn wxtian@mailst.xjtu.edu.cn 1 1 1 1 2 Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China; Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China; Department of Nuclear Reactor Engineering Design, China Institute of Atomic Energy, Beijing 102413, China Department of Nuclear Reactor Engineering Design, China Institute of Atomic Energy, Beijing 102413, China 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. China Advanced Research Reactor Natural circulation capacity Steady state characteristics References Ishii M , Kataoka I . Nuclear Engineering and Design , 1984 , 81 : 411 - 425 . Nuclear Engineering and Design Zvirin Y , Duffey C W , Duffey R B . Experimental and analytical investigation of a PWR natural circulation loop . 1980 , NP-1364-SR . Experimental and analytical investigation of a PWR natural circulation loop Kim M J , Lee Y B . International Journal on Heat Mass Transfer , 2001 , 44 : 389 - 397 . International Journal on Heat Mass Transfer Misale M , Frogheri M . International Comm. Heat Mass Transfer , 1999 , 26 ( 5 ): 597 - 606 . International Comm. Heat Mass Transfer Ramsom 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 .. Code structure, systems models, and solution method Jiang S Y . Kerntechnik , 1998 , 63 : 132 - 138 . Kerntechnik Yang Z M , Huang Y P , Wang F , et al . Nuclear Power Engineering , 1999 , 20 : 219 - 222 . Nuclear Power Engineering Sudo Y , Kaminaga M . Transaction of ASME, Journal of Heat Transfer , 1987 , 6 ( 4 ): 415 - 426 . Transaction of ASME, Journal of Heat Transfer Kanminaga M . JAERI-M , 1990 , 90 ( 21 ): 2201 - 2213 . JAERI-M 10.1016/S1001-8042(07)60044-X TL333 2006-12-13 2007-06-20 2021-01-19 2007 Nuclear Science and Techniques 03 18