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Yang X, Jiang SY, Zhang Y. Experimental and numerical investigation of sub-cooled boiling, condensation, and void flashing in nuclear heating reactor test loop. KERNTECHNIK 2022. [DOI: 10.1515/kern-2002-0041] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
This paper describes experimental and numerical investigations of sub-cooled boiling, condensation, and void flashing in the HRTL-5 test loop, which simulates the primary loop of a 5 MW nuclear heating reactor. A drift-flow model of two-phase with four governing equations was used, in which sub-cooled boiling, condensation, and void flashing have been taken into account. Based on the mathematical model, a program has been developed for analyzing the natural circulation system. As parameters, inlet sub-cooling, system pressure, and heat flux are varied. For comparison, some simplified models, which are designed to reveal the importance of sub-cooled boiling, condensation, flashing in the HRTL-5 test loop, are adopted in the program. The results show: (1) sub-cooled boiling, condensation, and void flashing may have great influence on the distribution of the void fraction and more intense at low system pressure; (2) the calculation of them is correlative and interactive other than independent; (3) for a system with short heated section, long riser, and low pressure, it is possible to reach “boiling out of the core”, where there is almost no void in the heated section, but much in the riser.
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Affiliation(s)
- X. Yang
- Institute of Nuclear Energy Technology of Tsinghua University , Beijing , 100084 , China
| | - S. Y. Jiang
- Institute of Nuclear Energy Technology of Tsinghua University , Beijing , 100084 , China
| | - Y. Zhang
- Institute of Nuclear Energy Technology of Tsinghua University , Beijing , 100084 , China
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Guo X, Sun Z, Wang J, Yu S. Steady-state performances and scaling analyses for an open flashing-driven natural circulation system. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.11.007] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Guo X, Sun Z, Wang J, Yu S, Gao L. Numerical simulation of the transient behaviors in an open natural circulation system with a large scale. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.10.026] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Analytical modeling of flashing-induced instabilities in a natural circulation cooled boiling water reactor. NUCLEAR ENGINEERING AND DESIGN 2002. [DOI: 10.1016/s0029-5493(02)00043-2] [Citation(s) in RCA: 38] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Jiang S, Zhang Y, Wu X, Bo J, Jia H. Flow excursion phenomenon and its mechanism in natural circulation. NUCLEAR ENGINEERING AND DESIGN 2000. [DOI: 10.1016/s0029-5493(00)00301-0] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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