Conceptual and preliminary engineering design of experimental helium loop for China HCCB TBM components test

被引:7
|
作者
Xiang, B. [1 ]
Ye, X. F. [1 ]
Feng, K. M. [1 ]
机构
[1] SW Inst Phys, Fus Reactor & Mat Div, Chengdu, Peoples R China
关键词
ITER port; CN HCCB TBM; Experimental helium loop; Thermal stress;
D O I
10.1016/j.fusengdes.2010.08.019
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
Chinese Helium Cooled Ceramic Breeder Test Blanket Module (CN HCCB TBM) had been confirmed to be one of the leader concepts, which will be tested in half of ITER equatorial port. It is responsible for each TBM does not jeopardize ITER operation. In order to ensure the future CN HCCB TBM safely and effectively operating in ITER, components and even full scale of TBM should be tested before delivery to ITER site. Therefore, a new high temperature and high pressure experimental helium loop will be constructed to validate the thermal-hydraulic and thermal-mechanical capability of those components. In this article, a rational conceptual design of the experimental helium loop was presented. At the same time, preliminary engineering design includes thermal-hydraulics assessment of equipments, thermal stress of pipes in the loop were performed. The assessment results show that technical issues of helium loop construction are expected to be solved successfully. Finally, possible test strategies have been presented to fulfill the TBM thermo-hydraulics campaigns. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:2146 / 2149
页数:4
相关论文
共 50 条
  • [31] SHOULD TEAMS COLLABORATE DURING CONCEPTUAL ENGINEERING DESIGN?: AN EXPERIMENTAL STUDY
    Gyory, Joshua T.
    Cagan, Jonathan
    Kotovsky, Kenneth
    PROCEEDINGS OF THE ASME INTERNATIONAL DESIGN ENGINEERING TECHNICAL CONFERENCES AND COMPUTERS AND INFORMATION IN ENGINEERING CONFERENCE, 2018, VOL 7, 2018,
  • [32] CONCEPTUAL ENGINEERING DESIGN STUDIES OF A FUSION EXPERIMENTAL POWER-REACTOR
    SAGER, PH
    JONZEN, M
    KEARNEY, D
    THOMAS, R
    TOFFOLO, W
    WOODS, T
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 25 - 27
  • [33] Structural design and preliminary analysis of liquid lead-lithium blanket for China Fusion Engineering Test Reactor
    Ni, Muyi
    Lian, Chao
    Zhang, Shichao
    Nie, Baojie
    Jiang, Jieqiong
    FUSION ENGINEERING AND DESIGN, 2015, 94 : 61 - 66
  • [34] Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor
    Dehong Chen
    Jieqiong Jiang
    Yawei Hou
    Wenxue Duan
    Muyi Ni
    Chao Xing
    Journal of Fusion Energy, 2015, 34 : 127 - 132
  • [35] Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor
    Chen, Dehong
    Jiang, Jieqiong
    Hou, Yawei
    Duan, Wenxue
    Ni, Muyi
    Xing, Chao
    JOURNAL OF FUSION ENERGY, 2015, 34 (01) : 127 - 132
  • [36] Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR
    Zhao, Wenlong
    Shi, Shanshuang
    Cheng, Yong
    Huang, Jianjun
    Sun, Huibin
    Pan, Hongtao
    Yang, Songzhu
    Zhang, Yu
    JOURNAL OF FUSION ENERGY, 2020, 39 (03) : 67 - 76
  • [37] Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR
    Wenlong Zhao
    Shanshuang Shi
    Yong Cheng
    Jianjun Huang
    Huibin Sun
    Hongtao Pan
    Songzhu Yang
    Yu Zhang
    Journal of Fusion Energy, 2020, 39 : 67 - 76
  • [38] Preliminary structural design and thermo-mechanical analysis of helium cooled solid breeder blanket for Chinese Fusion Engineering Test Reactor
    Li, Min
    Chen, Hongli
    Zhou, Guangming
    Liu, Qianwen
    Wang, Shuai
    Lv, Zhongliang
    Ye, Minyou
    FUSION ENGINEERING AND DESIGN, 2015, 91 : 39 - 43
  • [39] CONCEPTUAL DESIGN OF A FUSION ENGINEERING TEST FACILITY BASED ON MIRROR CONFINEMENT (FEF)
    HIRAYAMA, S
    KAWABE, T
    KOHZAKI, Y
    SAGAWA, H
    YOSHIKAWA, K
    ASAMI, N
    FUKAI, Y
    MIYASUGI, T
    MORINO, N
    FUSION ENGINEERING AND DESIGN, 1989, 9 : 395 - 399
  • [40] Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor
    Lei, Mingzhun
    Xu, Shuling
    Guo, Chao
    Liu, Sumei
    Song, Yuntao
    Lu, Kun
    Pei, Kun
    Xu, Kun
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (04) : 1657 - 1663