Numerical simulation of Loss-of-Flow transient in the MYRRHA reactor

被引:0
|
作者
Koloszar L. [1 ]
Planquart P. [1 ]
van Tichelen K. [2 ]
Keijers S. [2 ]
机构
[1] von Karman Institute, Chaussée de Waterloo 72, Rhode-St-Genèse
[2] SCK·CEN, Boeretang 200, Mol
基金
欧盟地平线“2020”;
关键词
9;
D O I
10.1016/j.nucengdes.2020.110675
中图分类号
学科分类号
摘要
The current paper describes the loss of flow (LOF) transient investigated in the MYRRHA reactor by the means of Computational Fluid Dynamics. This scenario is starting from the nominal operation case then the two pumps stop simultaneously. An unsteady solution with resolved interface was considered with calculating conjugate heat transfer through the relevant structures. Due to a postulated event (e.g. loss of the electric grid) the pumps are not powered anymore stops. After the detection of the problem (temperature difference above the core rises with 20 degree) the reactor power is stopped by the safety rods (delay of 1 s). The fuel elements, however, continue to generate residual heat according to the decay heat curve. Due to the loss of the pumps, the pressure difference between the cold and the hot plenum is decreasing, which result in a gravitational flow equilibrating the two free surfaces to the same level. The objective of the work was to determine the flow through the core during the coast down of the pumps and eventual flow reversal into the pump/heat-exchanger box due to the gravitational flow. The simulation revealed that after losing power, the LBE flow reverses into the pumps in less than 0.1 s according to the simulations. In the core there is a brief moment of reverse flow, too, but only after the core is scrammed, therefore, the loss of cold LBE flow is not causing overheat. Once the core is scrammed, the position of the maximum temperature in the system shifts to the Above Core Structure, where the residual hot plume rising from the core impinges to the Above Core Upper Closure. The levels of the lower and upper plenum equilibrate roughly 20 s after the pump failure event. © 2020 Elsevier B.V.
引用
收藏
相关论文
共 50 条
  • [41] Numerical Simulation of Transient Flow in Products Pipeline
    Wang Zhenye
    Li Jiangfei
    Yuan Lian
    Fu Zhizhong
    Li Bo
    Cheng Wenxue
    Jin Long
    Liu Lei
    THERMAL, POWER AND ELECTRICAL ENGINEERING, PTS 1 AND 2, 2013, 732-733 : 487 - +
  • [42] INHERENT ACCOMMODATION OF UNPROTECTED LOSS-OF-FLOW ACCIDENTS IN LMFBRS
    SU, SF
    SEVY, RH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 300 - 301
  • [43] BOILING INCOHERENCY EFFECTS IN UNPROTECTED LOSS-OF-FLOW ACCIDENTS
    THEOFANOUS, TG
    MIAO, C
    LOIS, L
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 537 - 538
  • [44] ANALYSIS OF THE BR2 LOSS-OF-FLOW TEST A
    Tzanos, Constantine P.
    Dionne, B.
    NUCLEAR TECHNOLOGY, 2011, 176 (01) : 93 - 105
  • [45] AN ANALYSIS OF INITIATING AND TRANSITION PHASES FOR AN UNPROTECTED LOSS-OF-FLOW ACCIDENT IN AN AXIALLY HETEROGENEOUS FAST BREEDER REACTOR CORE
    AZEKURA, K
    UMEGAKI, K
    INOUE, K
    RHOW, SK
    MCELROY, JE
    SWITICK, DM
    NUCLEAR TECHNOLOGY, 1987, 76 (03) : 325 - 336
  • [46] UNPROTECTED LOSS-OF-FLOW TRANSIENTS IN LARGE LMFBRS.
    Tzanos, C.P.
    Barthold, W.P.
    van Erp, J.B.
    1976, 3 : 1081 - 1090
  • [47] Numerical simulation on flow field of swimming pool reactor
    Wang, Jin-Hua
    Bo, Han-Liang
    Jiang, Sheng-Yao
    Zheng, Wen-Xiang
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2005, 39 (04): : 322 - 325
  • [48] Numerical simulation of flow and temperature field in MOCVD reactor
    Key Laboratory of Optic-Communication and Lightwave Technologies, Beijing University of Posts and Telecommunications, Beijing 100876, China
    Rengong Jingti Xuebao, 2008, 6 (1342-1348): : 1342 - 1348
  • [49] Numerical Simulation of Multiphase Flow in Anaerobic Baffled Reactor
    Zhou, Donghui
    Wu, Shiqiang
    Wang, Ze
    PROCEEDINGS OF THE 35TH IAHR WORLD CONGRESS, VOLS I AND II, 2013, : 3648 - 3654
  • [50] NUMERICAL SIMULATION OF FLOW IN A PHOTOCATALYTIC REACTOR CONTAINING BAFFLES
    Ahmed, Saber
    Rasul, M. G.
    Brown, R. J.
    Esteban Duran, J.
    PROCEEDINGS OF THE ASME/JSME/KSME JOINT FLUIDS ENGINEERING CONFERENCE 2011, VOL 1, PTS A-D, 2012, : 1487 - 1493