Thermalhydraulic Investigation Using a Test Facility Simulating 200 MW Integral Heating Reactor

スポンサーリンク

概要

• 論文の詳細を見る

• Since the middle of 1980’s, a research program on heating reactor has been carried out at Institute of Nuclear Energy Technology (INET) of Tsinghua University in China, the heating reactor is a light water cooled, integral type natural circulation reactor with low system pressure and low core exit quality, it has the passive safety features and other advanced characteristics of the next generation reactors. Because of a relatively long riser and low system pressure, a small quality perturbation at the exit of the core will lead to a relatively large variation of void fraction in the riser, so will the driving force. All of the above features made it very different from the typical PWRs and BWRs. In order to guarantee the safe operation of the heating reactor, a full scale test loop HRTL-200, simulating HR-200 heating reactors in main geometry and operation parameters, was constructed and operated under the broad test conditions covering the 200 MW heating reactor operation conditions at INET. The HRTL-200 test facility, some of steady-state and two-phase flow instability test results from the test facility and the consideration how to choose the optimal design parameters for the heating reactors are shown in this paper. The range of experimentally studied parameters are: the system pressure is from 1.0 to 4.0 MPa, the largest heat flux is about 50 W/cm2, and the quality at the exit of the test section is less than 6%.

• 社団法人 日本原子力学会の論文

著者

• Han Bin

  Institute Of Nuclear Energy Technology Tsinghua University

• Jia H

  Tsinghua Univ. Beijing Chn

• Jia Haijun

  Institute Nuclear Energy Technology Tsinghua University

• ZHANG Youjie

  Institute Nuclear Energy Technology, Tsinghua University

• Zhang Youjie

  Institute Of Nuclear Energy Technology Tsinghua University

• JIANG Shengyao

  Institute of Nuclear and New Energy Technology, the Key Laboratory of Advanced Reactor Engineering a

• WU Shaorong

  Institute of Nuclear Energy Technology, Tsinghua University

• LI Huaixuan

  Institute of Nuclear Energy Technology, Tsinghua University

• Li Huaixuan

  Institute Of Nuclear Energy Technology Tsinghua University

• Wu Shaorong

  Institute Of Nuclear Energy Technology Tsinghua University

• Jiang Shengyao

  Institute Of Nuclear And New Energy Technology The Key Laboratory Of Advanced Reactor Engineering An

• Jiang Shengyao

  Institute Of Nuclear And New Energy Technology Of Tsinghua University

• Zhang Youjie

  Institute Nuclear Energy Technology Tsinghua University

関連論文

• Gas Space and Flow Stability in Integrated Reactors
• Optimization of Hot Gas Chamber in High Temperature Reactor
• Numerical Analysis of the Lifting Beam's Influence on Flow Fields in Planar Fuel Assemblies
• Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) : Heat-transfer and Hydrodynamic Features of the Once-Through Steam Generator
• Experiment and Verification Test of the Once-through Steam Generator of the 10MW High-temperature Gas-cooled Reactor Flow Stability of the Once-through Steam Generator
• Thermalhydraulic Investigation Using a Test Facility Simulating 200 MW Integral Heating Reactor
• Review of Thermalhydraulic Experimental Researches at INET
• Two New Type Passive Residual Heat Removal Systems for Nuclear Reactors
• Experimental Investigation on Feasibility of Two-Region-Designed Pebble-Bed High-Temperature Gas-Cooled Reactor
• Two New Type Passive Residual Heat Removal Systems for Nuclear Reactors
• Numerical Analysis of the Lifting Beam's Influence on Flow Fields in Planar Fuel Assemblies

もっと見る 閉じる

スポンサーリンク