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Tas-Koehler S, Lecrivain G, Krepper E, Unger S, Hampel U. Numerical investigation on the effect of transversal fluid field deformation on heat transfer in a rod bundle with mixing vanes. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110575] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Kim J, Cho S, Park JK, Youn YJ, Moon SK. Experimental study to assess effects of ballooning and fuel relocation on the coolability of fuel rod bundle. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.013] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Hu Z, Li H, Tao J, Liu D, Gu H. Experimental study on heat transfer of supercritical water flowing upward and downward in 2 × 2 rod bundle with wrapped wire. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.08.042] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Nguyen NH, Kim J, Hong SH, Moon SK, Song CH. Improvements of COBRA-TF on the effect of flow blockage during a LB LOCA with consideration of fuel relocation phenomenon. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.08.015] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Lomperski S, Bremer N, Gerardi C. Distributed temperature sensing inside a 19-rod bundle. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.05.008] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Clément SA, Bardet PM. Surrogates for Single-Phase Conjugate Heat Transfer Validation Experiments at Light Water Reactor Prototypical Conditions. NUCL TECHNOL 2017. [DOI: 10.1080/00295450.2017.1327254] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- Simon A. Clément
- The George Washington University, Mechanical and Aerospace Engineering Department, Science and Engineering Hall, Suite 3000, 800 22nd Street NW, Washington, D.C. 20052
| | - Philippe M. Bardet
- The George Washington University, Mechanical and Aerospace Engineering Department, Science and Engineering Hall, Suite 3000, 800 22nd Street NW, Washington, D.C. 20052
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Wang X, Wang R, Du S, Chen J, Tan S. Flow visualization and mixing quantification in a rod bundle using laser induced fluorescence. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.007] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Moon SK, Kim J, Kim K, Kim BJ, Park JK, Youn YJ, Choi HS, Song CH. Reflood experiments in rod bundles with flow blockages due to clad ballooning. KERNTECHNIK 2016. [DOI: 10.3139/124.110744] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Clad ballooning and the resulting partial flow blockage are one of the major thermal-hydraulic concerns associated with the coolability of partially blocked cores during a loss-of-coolant accident (LOCA). Several in-pile tests have shown that fuel relocation causes a local power accumulation and a high thermal coupling between the clad and fuel debris in the ballooned regions. However, previous experiments in the 1980s did not take into account the fuel relocation phenomena and resulting local power increase in the ballooned regions. The present paper presents the results of systematic investigations on the coolability of rod bundles with flow blockages. The experiments were mainly performed in 5 × 5 rod bundles, 2 × 2 rod bundles and other test facilities. The experiments include a reflood heat transfer, single-phase convective heat transfer, flow redistributions phenomena, and droplet break-up behavior. The effects of the fuel relocation and resulting local power increase were investigated using a 5 × 5 rod bundle. The fuel relocation phenomena increase the peak cladding temperature.
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Affiliation(s)
- S. K. Moon
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - J. Kim
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - K. Kim
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - B. J. Kim
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - J. K. Park
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - Y. J. Youn
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - H. S. Choi
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
| | - C. H. Song
- Korea Atomic Energy Research Institute , Daeduk-daero 989-111, Yuseong-Gu, Daejeon, 305-353 , Republic of Korea
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Liu Q, Morooka S. Recent activities in the field of thermal hydraulic researches. J NUCL SCI TECHNOL 2014. [DOI: 10.1080/00223131.2014.924887] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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