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
下载
收藏
页码:209 / 215
页数:7
相关论文
共 50 条
  • [21] THERMAL-HYDRAULIC AND NEUTRONICS ANALYSIS OF AN SAP-THERMOSYPHON BLANKET
    FILLO, JA
    POWELL, JR
    LAZARETH, O
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 39 - 39
  • [22] Solid breeder test blanket module design and analysis
    Ying, A
    Abdou, M
    Calderoni, P
    Sharafat, S
    Youssef, M
    An, Z
    Abou-Sena, A
    Kim, E
    Reyes, S
    Willms, S
    Kurtz, R
    FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) : 659 - 664
  • [23] Development of thermal-hydraulic analysis methodology for multiple modules of water-cooled breeder blanket in fusion DEMO reactor
    Kim, Geon-Woo
    Lee, Jeong-Hun
    Cho, Hyoung-Kyu
    Park, Goon-Cherl
    Im, Kihak
    FUSION ENGINEERING AND DESIGN, 2016, 103 : 98 - 109
  • [24] Overview of pool hydraulic design of Indian prototype fast breeder reactor
    K. Velusamy
    P. Chellapandi
    S. C. Chetal
    Baldev Raj
    Sadhana, 2010, 35 : 97 - 128
  • [25] Overview of pool hydraulic design of Indian prototype fast breeder reactor
    Velusamy, K.
    Chellapandi, P.
    Chetal, S. C.
    Raj, Baldev
    SADHANA-ACADEMY PROCEEDINGS IN ENGINEERING SCIENCES, 2010, 35 (02): : 97 - 128
  • [26] THERMAL-HYDRAULIC ANALYSIS OF LOW ACTIVITY FUSION BLANKET DESIGNS.
    Fillo, J.A.
    Powell, J.
    Yu, W.S.
    American Society of Mechanical Engineers (Paper), 1977, (77 -HT-85):
  • [27] Thermal-hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system
    Wang, Jie
    Tian, Wenxi
    Su, Guanghui
    Qiu, Suizheng
    Xiang, Bin
    Zhang, Guoshu
    Feng, Kaiming
    FUSION ENGINEERING AND DESIGN, 2013, 88 (01) : 33 - 41
  • [29] NEUTRONIC AND THERMAL-HYDRAULIC ANALYSIS OF A FAST FISSION BLANKET FOR A FUSION REACTOR
    BENDER, DJ
    LEE, JD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 64 - 66
  • [30] Experimental Thermal-Hydraulic Testing of a Mock-Up of the Fuel-Breeder Pin Concept for the EU-DEMO HCPB Breeding Blanket
    Abou-Sena, Ali
    Ghidersa, Bradut-Eugen
    Zhou, Guangming
    Rey, Joerg
    Hernandez, Francisco A.
    Lux, Martin
    Schlindwein, Georg
    JOURNAL OF NUCLEAR ENGINEERING, 2023, 4 (01): : 11 - 27