Neutronic experiment and analyses of a hybrid tritium breeding blanket mockup for CFETR

被引:1
|
作者
Ma, Jimin [1 ]
An, Li [1 ]
He, Tie [1 ]
Zhu, Tonghua [1 ]
Guo, Haiping [1 ]
Han, Zijie [1 ]
Liu, Zhiyong [1 ]
Bai, Jiangbo [1 ]
Jiang, Li [1 ]
Huang, Hongwen [1 ]
Wang, Shaohua [1 ]
Guo, Haibing [1 ]
Li, Zhenghong [1 ]
机构
[1] Acad Engn Phys, Inst Nucl Phys & Chem, Mianyang 621900, Sichuan, Peoples R China
基金
中国国家自然科学基金;
关键词
Hybrid blanket; CFETR; DT neutronic experiment; Fission reaction rate; Activation reaction rate; Tritium production rate; BENCHMARK EXPERIMENT; REACTOR; ASSEMBLIES; URANIUM; DESIGN;
D O I
10.1016/j.anucene.2021.108431
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 experiment has been performed using DT neutrons on a blanket mockup of the hybrid tritium breeding blanket (HTBB) at CAEP. As a backup blanket configuration for CFETR, HTBB design which uses uranium alloy, water coolant and ceramic breeder pebble bed has been proposed to obtain high tritium breeding ratio. The experiment has provided validation not only to the preliminary design of HTBB, but also to calculation code and nuclear data used in the simulations. Various neutron responses such as fission reaction rate, plutonium production rate, activation reaction rate and tritium production rate (TPR) have been measured. Numerical analyses were carried out with MCNP-4C code using ENDF/B-VII.1, TENDL-2017, IRDFF-v1.05 and FENDL3.1 nuclear data libraries. The comparisons between the calculation and experimental results show an agreement within about 10% for most of the measured quantities. The ratios of calculated to measured results (C/E) of tritium production rate are in 0.98-1.04 range which shows good agreement. (C) 2021 Elsevier Ltd. All rights reserved.
引用
收藏
页数:11
相关论文
共 50 条
  • [1] Study on the temperature control mechanism of the tritium breeding blanket for CFETR
    Liu, Changle
    Qiu, Yang
    Zhang, Jie
    Zhang, Jianzhong
    Li, Lei
    Yao, Damao
    Li, Guoqiang
    Gao, Xiang
    Wu, Songtao
    Wan, Yuanxi
    [J]. NUCLEAR FUSION, 2017, 57 (12)
  • [2] Neutronic analyses of design issues affecting the tritium breeding performance in different DEMO blanket concepts
    Pereslavtsev, Pavel
    Bachmann, Christian
    Fischer, Ulrich
    [J]. FUSION ENGINEERING AND DESIGN, 2016, 109 : 1207 - 1211
  • [3] NEUTRONIC ANALYSES FOR CFETR WITH MODULAR HELIUM COOLED LITHIUM CERAMIC BLANKET
    Xu, Kun
    Ye, Minyou
    Song, Yuntao
    Lei, Mingzhun
    Mao, Shifeng
    [J]. PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5, 2017,
  • [4] Impact Analysis of Helium Cooled Solid Blanket Structures on the Tritium Breeding Performance in CFETR
    Zhongliang Lv
    Qin Zeng
    Wei Li
    Lei Pan
    Hongli Chen
    [J]. Journal of Fusion Energy, 2016, 35 : 689 - 693
  • [5] Impact Analysis of Helium Cooled Solid Blanket Structures on the Tritium Breeding Performance in CFETR
    Lv, Zhongliang
    Zeng, Qin
    Li, Wei
    Pan, Lei
    Chen, Hongli
    [J]. JOURNAL OF FUSION ENERGY, 2016, 35 (04) : 689 - 693
  • [6] Tritium transport analysis for CFETR WCSB blanket
    Zhao, Pinghui
    Yang, Wanli
    Li, Yuanjie
    Ge, Zhihao
    Nie, Xingchen
    Gao, Zhongping
    [J]. FUSION ENGINEERING AND DESIGN, 2017, 114 : 26 - 32
  • [7] Tritium transport analysis of HCPB blanket for CFETR
    Pan, Lei
    Chen, Hongli
    Zeng, Qin
    [J]. FUSION ENGINEERING AND DESIGN, 2016, 113 : 82 - 86
  • [8] Adaptation of the HCPB DEMO TBM as breeding blanket for ITER: Neutronic and thermal analyses
    Aquaro, D.
    Cerullo, N.
    Ciucci, I.
    Morellini, D.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2226 - 2232
  • [9] Study on Multiphysics Coupling and Automatic Neutronic Optimization for Solid Tritium Breeding Blanket of Fusion Reactor
    Qu, Shen
    Cao, Qixiang
    Duan, Xuru
    Wang, Xueren
    Wang, Xiaoyu
    [J]. ENERGIES, 2021, 14 (17)
  • [10] Neutronics analyses of COOL blanket for CFETR
    Wu, Qiuran
    Lu, Peng
    Zhang, Xiaokang
    Chen, Lei
    Liu, Songlin
    [J]. FUSION ENGINEERING AND DESIGN, 2022, 179