Experimental study of the coupled thermo-hydraulic-neutronic stability of a natural circulation HPLWR

被引:31
|
作者
T'Joen, C. [1 ,2 ]
Rohde, M. [1 ]
机构
[1] Delft Univ Technol, Dept Radiat Radionuclides & Reactors, NL-2629 JB Delft, Netherlands
[2] Univ Ghent, Dept Flow Heat & Combust Mech, B-9000 Ghent, Belgium
关键词
SUPERCRITICAL-PRESSURE; WATER-REACTOR; HEAT-TRANSFER; FLOW INSTABILITIES; CHANNELS; DESIGN; CORROSION; SYSTEM; FLUIDS; STATE;
D O I
10.1016/j.nucengdes.2011.10.055
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The HPLWR (high performance light water reactor) is the European concept design for a SCWR (supercritical water reactor). This unique reactor design consists of a three pass core with intermediate mixing plena. As the supercritical water passes through the core, it experiences a significant density reduction. This large change in density could be used as the driving force for natural circulation of the coolant, adding an inherent safety feature to this concept design. The idea of natural circulation has been explored in the past for boiling water reactors (BWR). From those studies, it is known that the different feedback mechanisms can trigger flow instabilities. These can be purely thermo-hydraulic (driven by the friction - mass flow rate or gravity - mass flow rate feedback of the system), or they can be coupled thermohydraulic-neutronic (driven by the coupling between friction, mass flow rate and power production). The goal of this study is to explore the stability of a natural circulation HPLWR considering the thermohydraulic-neutronic feedback. This was done through a unique experimental facility. DeLight, which is a scaled model of the HPLWR using Freon R23 as a scaling fluid. An artificial neutronic feedback was incorporated into the system based on the average measured density. To model the heat transfer dynamics in the rods, a simple first order model was used with a fixed time constant of 6s. The results include the measurements of the varying decay ratio (DR) and frequency over a wide range of operating conditions. A clear instability zone was found within the stability plane, which seems to be similar to that of a BWR. Experimental data on the stability of a supercritical loop is rare in open literature, and these data could serve as an important benchmark tool for existing codes and models. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:221 / 232
页数:12
相关论文
共 50 条
  • [1] Neutronic/thermo-hydraulic coupling behavior analysis of HPLWR
    Tang, Qi, 1600, Atomic Energy Press (48):
  • [2] Stability of natural circulation boiling water reactors: Part II - Parametric study of coupled neutronic-thermohydraulic stability
    van Bragt, DDB
    Van der Hagen, THJJ
    NUCLEAR TECHNOLOGY, 1998, 121 (01) : 52 - 62
  • [3] Development of a coupled neutronic/thermal-hydraulic tool with multi-scale capabilities and applications to HPLWR core analysis
    Monti, Lanfranco
    Starflinger, Joerg
    Schulenberg, Thomas
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (05) : 1579 - 1591
  • [4] An experimental parametric study on natural circulation BWRs stability
    Marcel, Christian P.
    Rohde, M.
    Van der Hagen, T. H. J. J.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 318 : 135 - 146
  • [5] Experimental and numerical investigation of natural circulation stability of the SHUNCL thermal-hydraulic loop
    Rabiee, Ataollah
    Mirzaee, Mohammad Mehdi
    Nematollahi, Mohammad Reza
    Atf, Alireza
    PROGRESS IN NUCLEAR ENERGY, 2016, 93 : 386 - 396
  • [6] Study on coupled neutronic and thermodynamic instabilities in a double rectangular channel natural circulation system under rolling motion
    Zhou, Ling-Lan
    Zhang, Hong
    Tan, Chang-Lu
    Dong, Hua-Ping
    Hedongli Gongcheng/Nuclear Power Engineering, 2013, 34 (SUPPL.1): : 55 - 60
  • [7] Neutronic/thermal-hydraulic coupling analysis of natural circulation IPWR under ocean conditions
    Xia, Genglei
    Wang, Bing
    Du, Xue
    Wang, Chenyang
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 92 - 101
  • [8] A linear stability analysis of supercritical water reactors, (II) coupled neutronic thermal-hydraulic stability
    Yi, TT
    Koshizuka, S
    Oka, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (12) : 1176 - 1186
  • [9] Experimental study of thermo-hydraulic characteristics of natural circulation loop at water and FC-72 boiling under atmospheric pressure
    Kaban'kov, O. N.
    Sukomel, L. A.
    Zubov, N. O.
    Yagov, V. V.
    INTERNATIONAL CONFERENCE PROBLEMS OF THERMAL PHYSICS AND POWER ENGINEERING (PTPPE-2017), 2017, 891
  • [10] Thermo-hydraulic experimental validation of an integrated modular small reactor operating in full power natural circulation
    YANG XingTuan
    REN Cheng
    LIU ZhiYong
    TU JiYuan
    JIANG ShengYao
    Science China(Technological Sciences), 2014, (01) : 1 - 8