Neutronics design of the low aspect ratio tokamak reactor, VECTOR

被引:14
|
作者
Nishitani, T [1 ]
Yamauchi, M
Nishio, S
Wada, A
机构
[1] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan
[2] Startcom Co Ltd, Tokai, Ibaraki 3191105, Japan
关键词
neutronics; VECTOR; tritium breeding ratio; shield; lithium lead; VH2;
D O I
10.1016/j.fusengdes.2005.09.059
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
A neutronic study has been carried out for VECTOR, which is a low aspect ratio tokamak with the aspect ratio of 2.3, to achieve simultaneously sufficient shielding for super-conducting toroidal field coils (TFCs) and tritium breeding ratio (TBR) larger than unity, using the three-dimensional Monte Carlo neutron transport code MCNP-4C. The tritium production is mainly made by outboard blankets consisting of the self-cooled lithium lead (LiPb) as tritium breeding and neutron multiplying material, and the reduced activation ferritic steel F82H as structural material. The inboard blanket consisting of vanadium hydrate (VH2) and F82H as structural material plays the role of radiation shield for the TFCs. Adding Be layers to the LiPb layers effectively improves the TBR. By employing a 0.8 m thick inboard blanket with a 0.13 m thick LiPb layer, sufficient shielding for the inboard TFC and a total TBR of 1.08 are achieved. (c) 2005 Published by Elsevier B.V.
引用
收藏
页码:1245 / 1249
页数:5
相关论文
共 17 条
  • [1] Design of the high-Tc superconducting TF coil for the tight aspect ratio tokamak power reactor (VECTOR)
    Ando, T
    Nishio, S
    Yoshimura, H
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2004, 14 (02) : 1481 - 1484
  • [2] Possibility of tritium self-sufficiency in low aspect ratio tokamak reactor with the outboard blanket only
    Hayashi, T.
    Tobita, K.
    Nishio, S.
    Sato, S.
    Nishitani, T.
    Yamauchi, M.
    FUSION ENGINEERING AND DESIGN, 2006, 81 (23-24) : 2779 - 2784
  • [3] A study regarding the optimal radial build of a low-aspect-ratio tokamak fusion system
    Hong, Bong Guen
    FUSION ENGINEERING AND DESIGN, 2018, 135 : 110 - 115
  • [4] Neutronics and pumping power analyses on the Tokamak reactor for the fusion-biomass hybrid concept
    Ibano, Kenzo
    Kasada, Ryuta
    Yamamoto, Yasushi
    Konishi, Satoshi
    FUSION ENGINEERING AND DESIGN, 2013, 88 (11) : 2881 - 2884
  • [5] Neutronics analysis of the conceptual design of a component test facility based on the spherical tokamak
    Zheng, S.
    Voss, G. M.
    Pampin, R.
    FUSION ENGINEERING AND DESIGN, 2010, 85 (10-12) : 2300 - 2304
  • [6] On the optimal radial build of a normal aspect ratio tokamak fusion system
    Hong, B. G.
    Kim, T. -H.
    FUSION ENGINEERING AND DESIGN, 2019, 139 (148-154) : 148 - 154
  • [7] Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium
    Zou, Xiaoliang
    Sun, Yanting
    Zeng, Qiusun
    Wen, Xiaojian
    Cao, Xiaogang
    Huang, Xi
    Liu, Yibao
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (12) : 5330 - 5338
  • [8] Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor
    Zou, Xiaoliang
    Sun, Yanting
    Yang, Bo
    Liu, Yibao
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (12) : 5014 - 5021
  • [9] Design of emergency shutdown system for the Tehran Research Reactor; Part I: Neutronics investigation
    Safarinia, M.
    Faghihi, F.
    Mirvakili, S. M.
    Fakhraei, A.
    ANNALS OF NUCLEAR ENERGY, 2017, 103 : 306 - 314
  • [10] Neutronics and nuclear data: achievements in computational simulations and experiments in support of fusion reactor design
    Fischer, U
    Batistoni, P
    Ikeda, Y
    Youssef, MZ
    FUSION ENGINEERING AND DESIGN, 2000, 51-52 : 663 - 680