Modeling of Forced and Natural Circulation Test Loop for a Pressurized Water Reactor using Thermal-Hydraulic Method

[1] Zvirin, Y., 1981. A review of natural circulation loops in pressurized water reactors and other systems, Nuclear Engineering and Design, 67, 2, 203-225. https://doi.org/10.1016/0029-5493(82)90142-X

[2] Grief, R., 1988. Natural circulation loops. Journal of Heat Transfer, 110, 1243 -1258. https://doi.org/ 10.1115/1.3250624

[3] Shi, S., Zhu, Q., Sun, X., Ishii, M., 2018.  Assessment of RELAP5/MOD3.2 for startup transients in a natural circulation test facility, Annals of Nuclear Energy, 112, 257-266. https://doi.org/10.1016/j.anucene.2017.10.012

[4] Cherubini, M., Giannotti, W., Araneo, D., D’Auria, F., 2008., Use of the natural circulation flow map for natural circulation systems evaluation, Science and Technology of Nuclear Installations, Article ID 479673. https://doi.org/ 10.1155/2008/479673

[5] D'Auria, F., 2021.Passive systems and nuclear thermal-hydraulics, Nuclear Engineering and Design, 385, 111513. https://doi.org/10.1016/j.nucengdes.2021.111513

[6] Juhn, P.E., Kupitz, J., Cleveland, J., Cho, B., Lyon, R.B., 2000. IAEA activities on passive safety systems and overview of international development, Nuclear Engineering and Design, 201, 1. https://doi.org/10.1016/S0029-5493(00)00260-0

[7] Di Maio, F., Pedroni, N., Tóth, B., Burgazzi, L., Zio, E., 2021. Reliability Assessment of Passive Safety Systems for Nuclear Energy Applications: State-of-the-Art and Open Issues, Energies, 14(15), 4688. https://doi.org/10.3390/en14154688

[8] Lu,  D.,  Xiao,  Z.,  Chen,  B., 2010. A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions, Nuclear Engineering and Design,  240, 11, 3851-3861. https://doi.org/10.1016/j.nucengdes.2010.08.012

[9] Mousavian, S.K., D’Auria, F., Salehi, M.A., 2004. Analysis of natural circulation phenomena in VVER-1000, Nuclear Engineering and Design, 229, 25–46. https://doi.org/ 10.1016/j.nucengdes.2003.11.012

[10] Cherubini, M., D 'auria, F., Ferreri, J.C., Mazzantini, O., 2005. RELAP5 simulation of a natural circulation test in the PSB-VVER test facility, The 11th Int. Topical Meeting Nucl. Reactor Thermal-Hydraulics (NURETH-11), At Popes’ Palace Conference Center, Avignon, France, Vol: Paper 542.

[11] Gou, J., Qiu, S., Su, G., Jia, D., 2009.  Thermal hydraulic analysis of a passive residual heat removal system for an integral pressurized water reactor. Science and Technology of Nuclear Installations, ID 473795. https://doi.org/10.1155/2009/473795

[12] Liu, T.J., Lee, C.H., Way, Y.S., 1997. IIST and LSTF counterpart test on PWR station blackout transient, Nuclear Engineering and Design, 167(3) 357-373. https://doi.org/10.1016/s0029-5493(96)01302-7

[13] Liu, T.J., Lee, C.H., 2004. Adequacy of Power-to-Mass scaling in simulating PWR incident transient for Reduced-Height, Reduced-Pressure and Full-Height, Full Pressure Integral System Test facilities. Nuclear Science and Engineering, 146 274-290. https://doi.org/10.13182/NSE04-A2410

[14] Jafari, J., D’Auria, F., Kazeminejad, H., Davilu, H., 2002. Code-based design and stability analysis of a low pressure natural circulation test loop. International Journal of Heat and Technology, 20(2) 81-88. http://hdl.handle.net/11568/71077

[15] Bae, B.U., Lee K.H., Kim, Y.S., Yun, B.J., Park, G.C., 2008.  Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA, Nuclear Engineering and Design, 238, 2197–2205. https://doi.org/10.1016/j.nucengdes.2008.03.015

[16] D’Auria, F., Galassi, G.M., 2010. Scaling in nuclear reactor system thermal-hydraulics, Nuclear Engineering and Design, 240, 3267-3293. https://doi.org/10.1016/j.nucengdes.2010.06.010

[17] Zubair, M., Al Suwaidi, R. R., Al Souqi, A. A., 2021. Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software, Progress in Nuclear Energy, 141, 103949. https://doi.org/10.1016/j.pnucene.2021.103949

[18] Jianbang, W., Mingguang, Z., Minglu , W., Shufeng, Z., Xiangyun, Z., 2020. Research on thermal hydraulic characteristics of integrated reactor in natural circulation operation under ocean motions. Progress in Nuclear Energy,126, 103399. https://doi.org/10.1016/j.pnucene.2020.103399

[19] Nematollahi, M., Khonsha, B., Jahanfarnia, G., Sepanloo, K., Khonsha, I., 2021. ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant. Kerntechnik, 86(6) 445-453. https://doi.org/10.1515/kern-2020-0059

[20] Farhami, N., Bozorgian, A., 2011. Factors affecting selection of tubes of heat exchanger. In International Conference on Chemistry and Chemical Process IPCBEE (Vol. 10, pp. 223-228).

[21] Bozorgian, A., Ghazinezhad, M., 2018. A case study on causes of scale formation-induced damage in boiler tubes. Journal of Biochemical Technology, 2, 149-153.

[22] Bozorgian, A., Arab Aboosadi, Z., Mohammadi, A., Honarvar, B., Azimi, A. R., 2022. Statistical analysis of the effects of aluminum oxide (Al2O3) nanoparticle, TBAC, and APG on storage capacity of CO2 hydrate formation. Iranian Journal of Chemistry and Chemical Engineering, 41(1), 220-231. https://doi.org/10.30492/ijcce.2020.125267.4096

[23] Zilabi, S., Shareei, M., Bozorgian, A., Ahmadpour, A., Esmaeil, E., 2022. A review on nanoparticle application as an additive in lubricants. Advanced Journal of Chemistry, Section B: Natural Products and Medical Chemistry, 4, 209-221. https://doi.org/10.22034/ajcb.2022.353097.1125

 [24] Ghanavati, B., Bozorgian, A., Ghanavati, J., 2022. Removal of copper (II) ions from the effluent by carbon nanotubes modified with tetrahydrofuran. Chemical Review and Letters, 5(1), 68-75. https://doi.org/10.22034/CRL.2022.326950.1152

[25] IAEA., 2005 Pressurized Water Reactor Simulator, Workshop material, Second edition, Vienna.

[26] Khonsha, B., Jahanfarnia, G., Sepanloo, K., Nematollahi, M., 2019. Scaling and thermal-hydraulic design of a test loop for the VVER-1000 reactor. Progress in Nuclear Energy, 113, Pages 18-27. https://doi.org/10.1016/j.pnucene.2019.01.007

[27] Pressure Drop Online-Calculator, www.pressure-drop.com/Online-Calculator

[28] The RELAP5 Code Development Team, 1995.   RELAP5/MOD3 Code Manual, NUREG/CR-5535 (INEL-95/0174), Vol: I-V. Idaho Nat Eng Lab. Idaho Falls, Idaho.