1
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Experimental study on heat transfer characteristics of separated heat pipe with compact structure for spent fuel pool. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109580] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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2
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Surip W, Putra N, Antariksawan AR. Design of passive residual heat removal systems and application of two-phase thermosyphons: A review. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104473] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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3
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Sun K, Wu Y, Qian F, Jung H, Kaluvan S, Huijin H, Zhang C, Reed FK, Nance Ericson M, Zhang H, Zuo L. Self-powered Through-wall communication for dry cask storage monitoring. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109306] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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4
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Investigation on thermal-hydraulic characteristics of the spent fuel pool with a complete passive cooling system. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109326] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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5
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Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109166] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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6
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Experimental Study on Separate Heat Pipe-type Passive Residual Heat Removal System of Swimming Pool-type Low-Temperature Heating Reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111743] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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7
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Dynamic modeling and controlling of a spent nuclear fuel storage pool under periodic operation and station blackout conditions. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108751] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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8
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Experimental Investigation of the Heat Transfer Characteristics and Operation Limits of a Fork-Type Heat Pipe for Passive Cooling of a Spent Fuel Pool. ENERGIES 2021. [DOI: 10.3390/en14237862] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
A fork-type heat pipe (FHP) is a passive heat-transport and air-cooling device used to remove the decay heat of spent nuclear fuels stored in a liquid pool during a station blackout. FHPs have a unique geometrical design to resolve the significant mismatch between the convective heat transfer coefficients of the evaporator and condenser parts. The evaporator at the bottom is a single heat-exchanger tube, whereas the condenser at the top consists of multiple finned tubes to maximize the heat transfer area. In this study, the heat transfer characteristics and operating limits of an FHP device were investigated experimentally. A laboratory-scale model of an FHP was manufactured, and a series of tests were conducted while the temperature was varied to simulate a spent fuel pool. As an index of the average heat transfer performance, the loop conductance was computed from the measurement data. The results show that the loop conductance of the FHP increased with the heat transfer rate but deteriorated significantly at the operating limit. The maximum attainable heat transfer rate of the unit FHP model was accurately predicted by the existing correlations of the counter-current flow limit for a single-rod-type heat pipe. In addition, the instant heat transfer behaviors of the FHP model under different temperature conditions were examined to interpret the measured loop conductance variation and operating limit.
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9
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Experimental study on the advective heat flux of a heat exchanger for passive cooling of spent fuel pools by temperature anemometry grid sensor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111237] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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10
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Choi J, Lim C, Kim H. Fork-end heat pipe for passive air cooling of spent nuclear fuel pool. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111081] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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11
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Depth-adaptive controller for spent nuclear fuel inspections. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.01.019] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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12
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Unger S, Krepper E, Beyer M, Hampel U. Numerical optimization of a finned tube bundle heat exchanger arrangement for passive spent fuel pool cooling to ambient air. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110549] [Citation(s) in RCA: 14] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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13
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Höhne T. Simulation of coolant mixing in a BWR spent fuel storage pool and flood chamber. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110468] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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14
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Performance of a passive cooling system for spent fuel pool using two-phase thermosiphon evaluated by RELAP5/MELCOR coupling analysis. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.024] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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15
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Two-scale CFD analysis of a spent fuel pool involving partially uncovered fuel storage racks. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2018.10.014] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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16
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17
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Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.005] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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18
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Unger S, Krepper E, Hampel U. Numerical analysis of heat exchanger designs for passive spent fuel pool cooling to ambient air. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.04.011] [Citation(s) in RCA: 21] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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19
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Gao S, Lu DG, Wang H, Cao Q, Han YD. Experimental investigation on the distribution of spray water in a spent fuel-assembly simulator. KERNTECHNIK 2018. [DOI: 10.3139/124.110879] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
The spent fuel pool cooling system in a nuclear power plant, which is comprised mainly by the cooling pumps and heat exchangers, ensures the safety of the spent fuel assemblies and the integrity of the fuel rods during the period of storage. With the development of the passive cooling technique, a spray cooling system for the spent fuels based on the gravity was designed to further enhance the safety of the spent fuel pool in case of accident conditions. This paper presents an experimental investigation of the validity of the spray-cooling system using two types of tight rod bundles, namely a 5 × 5 heated rod bundle and a 17 × 17 isothermal rod bundle. Results shows that the rod bundle heated with a lower power can be effectively cooled only by air without any spray water. With the increase of the heated power, the rod surface temperature increases gradually and the spray cooling has to be implemented to maintain the wall temperature at a certain level. The effect of flow rate on wall temperature was investigated. For the isothermal rod bundle, main interests were focused on the distribution of the spray water after it flowed along the rods.
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Affiliation(s)
- Sh. Gao
- Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy , North China Electric Power University, Beijing 102206 , P.R. China
| | - D. G. Lu
- Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy , North China Electric Power University, Beijing 102206 , P.R. China
| | - H. Wang
- Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy , North China Electric Power University, Beijing 102206 , P.R. China
| | - Q. Cao
- Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy , North China Electric Power University, Beijing 102206 , P.R. China
| | - Y. D. Han
- Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy , North China Electric Power University, Beijing 102206 , P.R. China
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20
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Ramadan A, Hasan R, Penlington R. Zero-dimensional transient model of large-scale cooling ponds using well-mixed approach. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.12.043] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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21
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Lai K, Wang W, Yi C, Kuang Y, Ye C. The study of passive cooling system assisted with separate heat pipe for decay heat removal in spent fuel pool. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.08.062] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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22
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Wang C, Liu L, Liu M, Zhang D, Tian W, Qiu S, Su G. Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.035] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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23
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24
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Chen YS, Yuann YR. Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.026] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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25
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Graževičius A, Kaliatka A. Modelling of the spent fuel heat-up in the spent fuel pools using one-dimensional system codes and CFD codes. KERNTECHNIK 2017. [DOI: 10.3139/124.110795] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractThe main functions of spent fuel pools are to remove the residual heat from spent fuel assemblies and to perform the function of biological shielding. In the case of loss of heat removal from spent fuel pool, the fuel rods and pool water temperatures would increase continuously. After the saturated temperature is reached, due to evaporation of water the pool water level would drop, eventually causing the uncover of spent fuel assemblies, fuel overheating and fuel rods failure. This paper presents an analysis of loss of heat removal accident in spent fuel pool of BWR 4 and a comparison of two different modelling approaches. The one-dimensional system thermal-hydraulic computer code RELAP5 and CFD tool ANSYS Fluent were used for the analysis. The results are similar, but the local effects cannot be simulated using a one-dimensional code. The ANSYS Fluent calculation demonstrated that this three-dimensional treatment allows to avoid the need for many one-dimensional modelling assumptions in the pool modelling and enables to reduce the uncertainties associated with natural circulation flow calculation.
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Affiliation(s)
- A. Graževičius
- 1PhD student, Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute Breslaujos str. 3, LT-44403 Kaunas, Lithuania
| | - A. Kaliatka
- 2Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute Breslaujos str. 3, LT-44403 Kaunas, Lithuania
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Investigation of the Thermal Performance of a Vertical Two-Phase Closed Thermosyphon as a Passive Cooling System for a Nuclear Reactor Spent Fuel Storage Pool. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2016.10.008] [Citation(s) in RCA: 34] [Impact Index Per Article: 4.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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27
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28
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Lu DG, Wang Y, Zhong HL, Duan XH, Cao Q. A spray cooling technique for spent fuel assembly stored in pool. KERNTECHNIK 2016. [DOI: 10.3139/124.110689] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
For the safety of spent nuclear fuel assemblies stored in storage pool in the extreme condition where the water is lost completely, a passive spray cooling technique was designed, and its effectiveness has been validated by a functional experiment. The spray cooling characteristics of the spent fuel assembly have also been investigated by the experiment.
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Affiliation(s)
- Dao-Gang Lu
- School of Nuclear Science and Engineering , Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Hokuno road No. 2, Zhanxiou Village, Changping district, Beijing, 102206, People's Republic of China , E-mail:
| | | | | | | | - Q. Cao
- School of Nuclear Science and Engineering , Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Hokuno road No. 2, Zhanxiou Village, Changping district, Beijing, 102206, People's Republic of China , E-mail:
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29
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Kondo M, Yoneda K, Furuya M, Nishi Y. An evaluation model to predict steam concentration in a BWR reactor building. J NUCL SCI TECHNOL 2015. [DOI: 10.1080/00223131.2014.1000993] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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30
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Fu W, Li X, Wu X, Zhang Z. Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.05.026] [Citation(s) in RCA: 25] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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31
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Xiong Z, Wang M, Gu H, Ye C. Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.03.045] [Citation(s) in RCA: 18] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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32
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Xiong Z, Ye C, Wang M, Gu H. Experimental study on the sub-atmospheric loop heat pipe passive cooling system for spent fuel pool. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2014.10.015] [Citation(s) in RCA: 26] [Impact Index Per Article: 2.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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33
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Kuang Y, Wang W, Zhuan R, Yi C. Simulation of boiling flow in evaporator of separate type heat pipe with low heat flux. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.08.008] [Citation(s) in RCA: 19] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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34
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The thermal performance of a loop-type heat pipe for passively removing residual heat from spent fuel pool. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.09.022] [Citation(s) in RCA: 21] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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35
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Chen S, Lin W, Ferng Y, Chieng C, Pei B. CFD simulating the transient thermal–hydraulic characteristics in a 17 × 17 bundle for a spent fuel pool under the loss of external cooling system accident. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2014.06.054] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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36
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Оgnerubov V, Кaliatka А, Vileiniškis V. Features of modelling of processes in spent fuel pools using various system codes. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2014.06.021] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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37
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Development of 3-D CFD methodology to investigate the transient thermal-hydraulic characteristics of coolant in a spent fuel pool. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.05.020] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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