• High Power Laser and Particle Beams
  • Vol. 34, Issue 5, 056006 (2022)
Xu Wang, Ya’nan Zhao*, Pengcheng Zhao, and Tao Yu
Author Affiliations
  • School of Nuclear Science and Technology, University of South China, Hengyang 421200, China
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    DOI: 10.11884/HPLPB202234.210474 Cite this Article
    Xu Wang, Ya’nan Zhao, Pengcheng Zhao, Tao Yu. Asymmetrical operation characteristics of natural circulation lead-bismuth reactor under ocean conditions[J]. High Power Laser and Particle Beams, 2022, 34(5): 056006 Copy Citation Text show less
    References

    [2] Wang Zeming. Numerical simulation of steam generat heat transfer acteristics in VVER1000 asymmetric operation[D]. Harbin: Harbin Institute of Technology, 2016

    [3] Cheng Jianping. Numerical simulation on fourloop PWR at asymmetric operation conditions based on CFD[D]. Harbin: Harbin Institute of Technology, 2015

    [5] Orlova E E, Smirnov V P, Vlasenko A E, et al. Celsist subchannel module aided simulation of liquid-metal coolant flow in experimental FA[J]. Atomic Energy, 128, 71-77(2020).

    [6] Martelli D, Forgione N, Di Piazza I, et al. HLM fuel pin bundle experiments in the CIRCE pool facility[J]. Nuclear Engineering and Design, 292, 76-86(2015).

    [8] Kumari I, Khanna A. Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility[J]. Nuclear Engineering and Design, 314, 217-226(2017).

    [9] Angelucci M, Martelli D, Barone G, et al. STH-CFD codes coupled calculations applied to HLM loop and pool systems[J]. Science and Technology of Nuclear Installations, 2017, 1936894(2017).

    [10] Ishida I, Tomiai I. Development of analysis code f thermal hydrodynamics of marine react under multidimensional ship motions, RETRAN02GRAV[R]. Tokyo: Atomic Energy Research Inst, 1992: 135.

    [11] Wang Bing. The development of a thermal hydraulic analysis code of nuclear react under ocean conditions[D]. Harbin: Harbin Engineering University, 2017

    [13] Murata H, Sawada K I, Kobayashi M. Experimental investigation of natural convection in a core of a marine reactor in rolling motion[J]. Journal of Nuclear Science and Technology, 37, 509-517(2000).

    [14] Ishida T, Yoritsune T. Effects of ship motions on natural circulation of deep sea research reactor DRX[J]. Nuclear Engineering and Design, 215, 51-67(2002).

    [16] Liu Peiqi. Preliminary study on physicalthermal coupling technology of integrated react under rolling conditions[D]. Hengyang: University of South China, 2019

    [17] Zheng Yuntao. A numerical analysis of asymmetric operation on the small nuclear reacts[D]. Harbin: Harbin Engineering University, 2014

    [18] Um K S, Ryu S H, Choi Y S, et al. Experimental and computational study of the core inlet temperature pattern under asymmetric loop conditions[J]. Nuclear Technology, 125, 305-315(1999).

    [19] Grudev P, Pavlova M. Simulation of loss-of-flow transient in a VVER-1000 nuclear power plant with RELAP5/MOD3.2[J]. Progress in Nuclear Energy, 45, 1-10(2004).

    [20] Espinoza S, Hugo V, Böttcher M. Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS[J]. Progress in Nuclear Energy, 48, 865-879(2006).

    [21] Fazio C, Sobolev V, Aerts A, et al. Hbook on leadbismuth eutectic alloy lead properties, materials compatibility, thermalhydraulics technologies[R]. ISBN 9789264990029. OECDNEA, 2015.

    [22] The RELAP53D Code Development Team. RELAP53D code manual volume IV: models crelations[R]. INEELEXT9800834.

    [23] Borishanskii V M, Gotovskii M A, Firsova É V. Heat transfer to liquid metals in longitudinally wetted bundles of rods[J]. Soviet Atomic Energy, 27, 1347-1350(1969).

    [24] Rehme K. Pressure drop performance of rod bundles in hexagonal arrangements[J]. International Journal of Heat and Mass Transfer, 15, 2499-2517(1972).

    [25] Wen Jun. Analysis optimization of flow distribution f the CiADS leadbased react ce[D]. Lanzhou: University of Chinese Academy of Sciences (Institute of Modern Physics, Chinese Academy of Sciences, 2021

    [26] Grishchenko D, Jeltsov M, Kööp K, et al. The TALL-3D facility design and commissioning tests for validation of coupled STH and CFD codes[J]. Nuclear Engineering and Design, 290, 144-153(2015).

    [27] Papukchiev A, Jeltsov M, Kööp K, et al. Comparison of different coupling CFD–STH approaches for pre-test analysis of a TALL-3D experiment[J]. Nuclear Engineering and Design, 290, 135-143(2015).

    [28] Kp K. Application of a system thermalhydraulics code to development of validation process f coupled STHCFD codes[D]. ISBN 9789177297277 , 2018.

    [29] Grishchenko D, Papukchiev A, Liu Chunyu, et al. TALL-3D open and blind benchmark on natural circulation instability[J]. Nuclear Engineering and Design, 358, 110386(2020).

    [30] Wang Zhanwei. The flow heat transfer acteristics f low flow rate flow under rolling motion conditions[D]. Harbin: Harbin Engineering University, 2013

    [31] Ishida I, Kusunoki T, Murata H, et al. Thermal-hydraulic behavior of a marine reactor during oscillations[J]. Nuclear Engineering and Design, 120, 213-225(1990).

    Xu Wang, Ya’nan Zhao, Pengcheng Zhao, Tao Yu. Asymmetrical operation characteristics of natural circulation lead-bismuth reactor under ocean conditions[J]. High Power Laser and Particle Beams, 2022, 34(5): 056006
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