Overview of design and thermal-hydraulic analysis of Indian solid breeder blanket concept

被引:16
|
作者
Chaudhuri, Paritosh [1 ]
Danani, Chandan [1 ]
Chaudhari, Vilas [1 ]
Kumar, E. Rajendra [1 ]
机构
[1] Inst Plasma Res, Bhat 382428, Gandhinagar, India
关键词
DEMO; Ceramic breeder; Thermal-hydraulics; Helium-cooled Ceramic Breeder (HCCB);
D O I
10.1016/j.fusengdes.2013.02.023
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
India has developed two concepts of breeding blanket for the DEMO reactor: one is Lead Lithium Ceramic Breeder (LLCB), and the other one is Helium-cooled Ceramic Breeder (HCCB) concept. Indian HCCB concept is having edge on configuration of helium-cooled solid breeder with RAFMS structure. Li2TiO3/Li4SiO4 and beryllium are used as the tritium breeder and neutron multiplier, respectively. 2D thermal-hydraulic simulation studies using ANSYS have been performed based on the heat load obtained from neutronics calculations to confirm heat removal under ITER pulsed operation. Transient thermal analysis has been simulated in ANSYS for the ITER relevant operational conditions. Thermal analysis provides important information about the temperature distribution in different materials used and their temperature-time histories. Result of thermal-hydraulic simulations shows that in each cycle, the maximum temperature of all materials remains same. The peak temperatures of all materials are well within their limiting value. Concept designs of HCCB blanket and its thermal hydraulic analysis will be presented in this paper. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:209 / 215
页数:7
相关论文
共 50 条
  • [41] PWR THERMAL-HYDRAULIC DESIGN
    GELLERSTEDT, JS
    MORGAN, CD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 803 - 805
  • [42] Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR
    Chen, Hongli
    Li, Min
    Lv, Zhongliang
    Zhou, Guangming
    Liu, Qianwen
    Wang, Shuai
    Wang, Xiaoliang
    Zheng, Jie
    Ye, Minyou
    FUSION ENGINEERING AND DESIGN, 2015, 96-97 : 89 - 94
  • [43] Core thermal-hydraulic design
    Takada, E
    Nakagawa, S
    Fujimoto, N
    Tochio, D
    NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) : 37 - 43
  • [44] Design and safety analysis of the helium cooled solid breeder blanket for CFETR
    Wang, S.
    Zhou, G.
    Lv, Z.
    Jin, C.
    Chen, H.
    KERNTECHNIK, 2016, 81 (02) : 192 - 196
  • [45] THERMO-HYDRAULIC ANALYSIS OF THE OPTIMIZED HELIUM COOLED SOLID BREEDER BLANKET FOR CFETR
    Cui, Shijie
    Zhang, Dalin
    Cheng, Jie
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 2, 2016,
  • [46] Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis
    Ciurluini, C.
    Narcisi, V
    Tincani, A.
    Ferrer, C. Ortiz
    Giannetti, F.
    FUSION ENGINEERING AND DESIGN, 2021, 171
  • [47] Thermal-hydraulic Design and Transient Analysis of Helium-cooled Solid Target for ADS
    Peng, Tianji
    Zhou, Zhiwei
    Gu, Long
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5, 2014,
  • [48] THERMAL-HYDRAULIC STUDY OF THE ESPRESSO BLANKET FOR A TANDEM MIRROR REACTOR
    RAFFRAY, AR
    HOFFMAN, MA
    FUSION TECHNOLOGY, 1986, 10 (03): : 1640 - 1645
  • [49] Design and thermal-hydraulic analysis for CFETR divertor Dome
    Zhang, Xiyang
    Mou, Nanyu
    Xu, Tiejun
    Yin, Lei
    Li, Lei
    Yao, Damao
    FUSION ENGINEERING AND DESIGN, 2023, 186
  • [50] THERMAL HYDRAULIC ANALYSIS OF THE BASIC BREEDER MODULE OF THE EUROPEAN CERAMIC BIT DEMO BLANKET
    CEVOLANI, S
    PROUST, E
    VALLETTE, F
    FUSION ENGINEERING AND DESIGN, 1991, 17 : 139 - 143