[논문]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

Kusuma, Mukhsinun Hadi; Putra, Nandy; Antariksawan, Anhar Riza; Susyadi, Susyadi; Imawan, Ficky Augusta

doi:10.1016/j.net.2016.10.008

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 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.49 no.3, 2017년, pp.476 - 483

Kusuma, Mukhsinun Hadi (Heat Transfer Laboratory, Department of Mechanical Engineering Universitas Indonesia) , Putra, Nandy (Heat Transfer Laboratory, Department of Mechanical Engineering Universitas Indonesia) , Antariksawan, Anhar Riza (Centre for Nuclear Reactor Safety and Technology, National Nuclear Energy Agency of Indonesia (BATAN)) , Susyadi, Susyadi (Centre for Nuclear Reactor Safety and Technology, National Nuclear Energy Agency of Indonesia (BATAN)) , Imawan, Ficky Augusta (Heat Transfer Laboratory, Department of Mechanical Engineering Universitas Indonesia)

Abstract ▼ AI-Helper

The decay heat that is produced by nuclear reactor spent fuel must be cooled in a spent fuel storage pool. A wickless heat pipe or a vertical two-phase closed thermosyphon (TPCT) is used to remove this decay heat. The objective of this research is to investigate the thermal performance of a prototype model for a large-scale vertical TPCT as a passive cooling system for a nuclear research reactor spent fuel storage pool. An experimental investigation and numerical simulation using RELAP5/MOD 3.2 were used to investigate the TPCT thermal performance. The effects of the initial pressure, filling ratio, and heat load were analyzed. Demineralized water was used as the TPCT working fluid. The cooled water was circulated in the water jacket as a cooling system. The experimental results show that the best thermal performance was obtained at a thermal resistance of $0.22^{\circ}C/W$, the lowest initial pressure, a filling ratio of 60%, and a high evaporator heat load. The simulation model that was experimentally validated showed a pattern and trend line similar to those of the experiment and can be used to predict the heat transfer phenomena of TPCT with varying inputs.

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문제 정의

From previous studies, it is known that a vertical TPCT for passive cooling of a nuclear SFSP has not yet been studied or used. The objective of this study was to investigate the thermal performance of a prototype model of a large-scale vertical TPCT designed as a passive cooling system for a nuclear research reactor SFSP. This research used experimental investigations and RELAP5/MOD 3.

제안 방법

The TPCT model of the RELAP5/MOD 3.2 simulation was validated with the experiment, and it can therefore be used to simulate TPCTs with different inputs.
To ensure that the heat load inside the evaporator was the net heat load, the heat loss that occurred in the TPCT system must be calculated. The analysis used empirical correlations for the external free convection flows for a vertical plate [23]. The long vertical cylinder was divided into many vertical plates, and the heat loss was calculated on each vertical plate.
2 simulations. The initial pressure, filling ratio, and heat load of the TPCT were used as the variables in this research. The experimental results were then used to validate the simulation model.
The second experiments were conducted by varying the TPCT initial pressure among －62 cmHg, －64 cmHg, and －66 cmHg. The constant parameters were a heat load of 187 W, a filling ratio of 60%, a cooling water mass flow rate of 1 L/min, and a temperature of 30℃.
The best thermal performance was achieved at the lowest initial pressure, at a filling ratio of 60%, and at a high evaporator heat load. The simulation model showed a pattern and trend line similar to those of the experiment, and thus the simulation can be used to simulate heat transfer phenomena with varying TPCT inputs.

이론/모형

2 is commonly used for thermal-hydraulics simulation of light water reactor coolant systems during postulated accidents. In this research, this code was used to simulate the TPCT as a prototype model for a nuclear reactor SFSP passive cooling system. The model has the same geometry as the test equipment.
The experimental data were recorded using a National Instrument data acquisition system. K type thermocouples with an accuracy of ±0.

후속연구

The vertical TPCT used as passive cooling for a spent fuel pool is large due to the spent fuel pool size. The future plan is to propose a large-scale vertical TPCT and to improve the vertical TPCT design for SFSP in order to determine the TPCT’s heat transfer characteristics.

참고문헌 (24)

C. Ye, M.G. Zheng, M.L. Wang, R.H. Zhang, Z.Q. Xiong, The design and simulation of a new spent fuel pool passive cooling system, Ann. Nucl. Energy 58 (2013) 124-131.

상세보기
B.S. Jackel, Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4, Nucl. Eng. Des. 283 (2015) 2-7.

상세보기
V. Оgnerubov, А. Кaliatka, V. Vileiniskis, Features of modelling of processes in spent fuel pools using various system codes, Ann. Nucl. Energy 72 (2014) 497-506.

상세보기
X. Wu, W. Li, Y. Zhang, W. Tian, G. Su, S. Qiu, Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5, Ann. Nucl. Energy 72 (2014) 198-213.

상세보기
V.L. Sailor, K.R. Perkins, J.R. Weeks, H.R. Connell, Severe accidents in spent fuel pools in support of generic safety, Issue 82, Brookhaven National Lab., Upton, NY (USA), Nuclear Regulatory Commission, Washington, DC (USA). Division of Reactor and Plant Systems, 1987.
E.D. Throm, Beyond design basis accidents in spent-fuel pools-generic Issue 82, Nucl. Eng. Des. 126 (1991) 333-359.

상세보기
D. Reay, R. McGlen, P. Kew, Heat Pipes: Theory, Design and Applications, Butterworth-Heinemann, Oxford, UK, 2013.
C. Byon, S.J. Kim, Capillary performance of bi-porous sintered metal wicks, Int. J. Heat Mass Transf. 55 (2012) 4096-4103.

상세보기
N. Putra, W.N. Septiadi, R. Saleh, R.A. Koestoer, S. Purbo Prakoso, The effect of CuO-water nanofluid and biomaterial wick on loop heat pipe performance, Adv. Mater. Res. 875 (2014) 356-361.
Y. Li, H. He, Z. Zeng, Evaporation and condensation heat transfer in a heat pipe with a sintered-grooved composite wick, Appl. Therm. Eng. 50 (2013) 342-351.

상세보기
N. Putra, W.N. Septiadi, H. Rahman, R. Irwansyah, Thermal performance of screen mesh wick heat pipes with nanofluids, Exp. Therm. Fluid Sci. 40 (2012) 10-17.

상세보기
N. Putra, W.N. Septiadi, R. Irwansyah, Effect of concentration and loading fluid of nanofluids on the thermal resistance of sintered powder wick heat pipe, Adv. Mater. Res. 651 (2013) 728-735.

상세보기
N. Putra, R. Saleh, W.N. Septiadi, A. Okta, Z. Hamid, Thermal performance of biomaterial wick loop heat pipes with waterbased Al2O3 nanofluids, Int. J. Therm. Sci. 76 (2014) 128-136.

상세보기
S.H. Noie, Heat transfer characteristics of a two-phase closed thermosyphon, Appl. Therm. Eng. 25 (2005) 495-506.

상세보기
A. Alizadehdakhel, M. Rahimi, A.A. Alsairafi, CFD modeling of flow and heat transfer in a thermosyphon, Int. Commun. Heat Mass Transf. 37 (2010) 312-318.

상세보기
S.H. Noie, S.Z. Heris, M. Kahani, S.M. Nowee, Heat transfer enhancement using $Al_2O_3$ /water nanofluid in a two-phase closed thermosyphon, Int. J. Heat Fluid Flow 30 (2009) 700-705.

상세보기
P.G. Anjakar, D.R.B. Yarasu, Experimental analysis of condenser length effect on the performance of thermosyphon, Int. J. Emerg. Technol. Adv. Eng. 2 (2012) 494-499.
K. Kafeel, A. Turan, Axi-symmetric simulation of a two phase vertical thermosyphon using Eulerian two-fluid methodology, Heat Mass Transf. 49 (2013) 1089-1099.

상세보기
Y.-H. Tung, R.W. Johnson, Y.-M. Ferng, C.-C. Chieng, Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA, Nucl. Eng. Des. 275 (2014) 80-90.

상세보기
W. Fu, X. Li, X. Wu, Z. Zhang, Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool, Ann. Nucl. Energy 85 (2015) 346-356.

상세보기
M.H. Kusuma, N. Putra, S. Widodo, A.R. Antariksawan, Simulation of heat flux effect in straight heat pipe as passive residual heat removal system in light water reactor using RELAP5 Mod 3.2, Appl. Mech. Mater. 819 (2016) 122-126.

상세보기
Z. Xiong, M. Wang, H. Gu, C. Ye, Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool, Ann. Nucl. Energy 83 (2015) 258-263.

상세보기
T.L. Bergman, F.P. Incropera, A.S. Lavine, Fundamentals of heat and mass transfer, John Wiley & Sons, New Jersey, USA, 2011.
D. Wang, Z. Liu, J. Shen, C. Jiang, B. Chen, J. Yang, Z. Tu, W. Liu, Experimental study of the loop heat pipe with a flat disk-shaped evaporator, Exp. Therm. Fluid Sci. 57 (2014) 157-164.

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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 원문보기

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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 원문보기

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