Simulation of Heat Flux Effect in Straight Heat Pipe as Passive Residual Heat Removal System in Light Water Reactor Using RELAP5 Mod 3.2

Abstract:

Heat pipe is considered being used as a passive system to remove residual heat that generated from reactor core when incident occur or from spent fuel pool. The present research is aimed to studying the characteristics of straight heat pipe as passive residual heat removal system. As an initial step, a numerical simulation was conducted to simulate the best experimental design set up being prepared for the next step of the research. The objective is to get the thermal hydraulic characteristic due to variation of heat flux of heat source. The thermal hydraulic RELAP5 MOD 3.2 code is used to simulate and analyze the straight heat pipe characteristics. Variations of heat flux are 1567 Watt/m², 3134 Watt/m², 4701 Watt/m², 6269 Watt/m², and 7837 Watt/m². Water as working fluid is heated on evaporation section with filling ratio 60%. Environmental air with variation 5 m/s and 10 m/s of velocity are used as external cooler. Straight heat pipe used in the simulation is wickless with 0.1 m of diameter and 6 m of length. The results show that higher heat flux given to the evaporator section will lead to more rapid heat transfer and achievement of steady state condition. The increasing of heat flux leads to an increase of evaporation of the working fluid and of pressure built in the heat pipe affecting higher saturation temperature of working fluid. Heat flux loading must consider the velocity of air as heat removal in the condenser to prevent dry out phenomenon in the evaporator. Based on the results, given the experimental set-up, the optimum range of experimental parameters could be determined.

• Periodical: Applied Mechanics and Materials (Volume 819)
• Pages: 122-126
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.819.122
• Online since: January 2016
• Authors: M. Hadi Kusuma*, Nandy Putra, Surip Widodo, Anhar Riza Antariksawan
• Keywords: Heat Flux, Passive System, Residual Heat, Straight Heat Pipe, Water Reactor

References

[1] Y. Wang, Preliminary Study for the Passive Containment Cooling System Analysis of the Advanced PWR, Energy Procedia, vol. 39, pp.240-247, / (2013).

DOI: 10.1016/j.egypro.2013.07.210

[2] IAEA, Passive Safety System and Natural Circulation in Wwater Cooled Nuclear Power Plants, IAEA-TECDOC-1624, (2009).

[3] X. -G. Yu, H. -S. Park, Y. -S. Kim, K. -H. Kang, S. Cho, and K. -Y. Choi, Systematic analysis of a station blackout scenario for APR1400 with test facility ATLAS and MARS code from scaling viewpoint, Nuclear Engineering and Design, vol. 259, pp.205-220, (2013).

DOI: 10.1016/j.nucengdes.2013.03.005

[4] Y. Li, H. -f. He, and Z. -x. Zeng, Evaporation and condensation heat transfer in a heat pipe with a sintered-grooved composite wick, Applied Thermal Engineering, vol. 50, pp.342-351, (2013).

DOI: 10.1016/j.applthermaleng.2012.07.042

[5] N. Putra, R. Saleh, W. N. Septiadi, A. Okta, and Z. Hamid, Thermal performance of biomaterial wick loop heat pipes with water-base Al2O3 nanofluids, International Journal of Thermal Sciences, vol. 76, pp.128-136, 2/ (2014).

DOI: 10.1016/j.ijthermalsci.2013.08.020

[6] D. Reay, R. McGlen, and P. Kew, Heat pipes: Theory, design and applications: Butterworth-Heinemann, (2013).

[7] C. Byon and S. J. Kim, Capillary performance of bi-porous sintered metal wicks, International Journal of Heat and Mass Transfer, vol. 55, pp.4096-4103, (2012).

DOI: 10.1016/j.ijheatmasstransfer.2012.03.051

[8] K. Ohashi, H. Hayakawa, M. Yamada, T. Hayashi, and T. Ishii, Preliminary study on the application of the heat pipe to the passive decay heat removal system of the modular HTR, Progress in Nuclear Energy, vol. 32, pp.587-594, (1998).

DOI: 10.1016/s0149-1970(97)00047-4

[9] D. Liu, G. -F. Tang, F. -Y. Zhao, and H. -Q. Wang, Modeling and experimental investigation of looped separate heat pipe as waste heat recovery facility, Applied Thermal Engineering, vol. 26, pp.2433-2441, (2006).

DOI: 10.1016/j.applthermaleng.2006.02.012

[10] P. Sabharwall, M. Patterson, V. Utgikar, and F. Gunnerson, Phase change heat transfer device for process heat applications, Nuclear Engineering and Design, vol. 240, pp.2409-2414, (2010).

DOI: 10.1016/j.nucengdes.2010.05.054

[11] R. Laubscher and R. T. Dobson, Theoretical and experimental modelling of a heat pipe heat exchanger for high temperature nuclear reactor technology, Applied Thermal Engineering, vol. 61, pp.259-267, (2013).

DOI: 10.1016/j.applthermaleng.2013.06.063

[12] T. Ishiguro, W. van Rooijen, Y. Shimazu, and H. Mochizuki, Design of a passive residual heat removal system for the FUJI-233Um molten salt reactor system, Annals of Nuclear Energy, vol. 64, pp.398-407, (2014).

DOI: 10.1016/j.anucene.2013.08.037

[13] K. Kafeel and A. Turan, Axi-symmetric simulation of a two phase vertical thermosyphon using Eulerian two-fluid methodology, Heat and Mass Transfer, vol. 49, pp.1089-1099, (2013).

DOI: 10.1007/s00231-013-1155-6

[14] Y. -H. Tung, R. W. Johnson, C. -C. Chieng, and Y. -M. Ferng, Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA, in ASME 2012 International Mechanical Engineering Congress and Exposition, 2012, pp.2341-2351.

DOI: 10.1115/imece2012-93007

[15] A. Alizadehdakhel, M. Rahimi, and A. A. Alsairafi, CFD modeling of flow and heat transfer in a thermosyphon, International Communications in Heat and Mass Transfer, vol. 37, pp.312-318, (2010).

DOI: 10.1016/j.icheatmasstransfer.2009.09.002

[16] C. Ye, M. Zheng, M. Wang, R. Zhang, and Z. Xiong, The design and simulation of a new spent fuel pool passive cooling system, Annals of Nuclear Energy, vol. 58, pp.124-131, (2013).

DOI: 10.1016/j.anucene.2013.03.007