Neutronic analyses of the HCPB DEMO reactor using a consistent integral approach

被引:33
|
作者
Pereslavtsev, Pavel [1 ]
Lu, Lei [1 ]
Fischer, Ulrich [1 ]
Bitz, Oliver [1 ]
机构
[1] Karlsruhe Inst Technol, Assoc KIT Euratom, D-76344 Karlsruhe, Germany
基金
欧盟地平线“2020”;
关键词
DEMO; Blanket; Neutronics; Monte Carlo; DESIGN;
D O I
10.1016/j.fusengdes.2013.12.019
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
This work is devoted to nuclear design analyses of the new HCPB-type DEMO reactor developed in the frame of the EFDA PPPT program. The neutronic simulations were carried out with the MCNP5 code using a full scale 3D torus sector model of the DEMO reactor. The model was generated with the McCad conversion tool from available CAD models using a consistent integral approach. The neutronic analyses addressed the tritium breeding performance, the nuclear power generation and the shielding capabilities of the reactor. Although tritium self-sufficiency was shown, the tritium breeding performance of the current design calls for further design improvements to arrive at a higher uncertainty margin. The shielding performance of the reactor is close to the limit. Sufficient shielding can be easily provided by a slight increase of the inboard shield thickness. (C) 2014 Karlsruhe Institute of Technology. Published by Elsevier B.V. All rights reserved.
引用
收藏
页码:1979 / 1983
页数:5
相关论文
共 50 条
  • [1] Neutronic analyses for the optimization of the advanced HCPB breeder blanket design for DEMO
    Pereslavtsev, Pavel
    Fischer, Ulrich
    Hernandez, Francisco
    Lu, Lei
    [J]. FUSION ENGINEERING AND DESIGN, 2017, 124 : 910 - 914
  • [2] 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
  • [3] Neutronic analysis of the HCPB TBM in ITER utilizing an advanced integral approach
    Pereslavtsev, P.
    Cismondi, F.
    Fischer, U.
    Grosse, D.
    Weber, V.
    [J]. FUSION ENGINEERING AND DESIGN, 2010, 85 (7-9) : 1653 - 1658
  • [4] Contribution to safety analyses of DEMO HCPB using AINA code
    Baeza, Eduard
    de Blas, Alfredo
    Riego, Albert
    Fabbri, Marco
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 146 : 64 - 68
  • [5] Analyses of the shielding options for HCPB DEMO blanket
    Pereslavtsev, Pavel
    Cismondi, Fabio
    Hernandez, Francisco A.
    [J]. FUSION ENGINEERING AND DESIGN, 2020, 156 (156)
  • [6] Comparative activation analyses for the HCPB breeding blanket in DEMO
    Park, Jin Hun
    Pereslavtsev, Pavel
    [J]. FUSION ENGINEERING AND DESIGN, 2021, 167
  • [7] Neutronic design analyses for a dual-coolant blanket concept: Optimization for a fusion reactor DEMO
    Palermo, I.
    Gomez-Ros, J. M.
    Veredas, G.
    Sanz, J.
    Sedano, L.
    [J]. FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 1019 - 1024
  • [8] Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor
    Zhou, Guangming
    Hernandez, Francisco
    Boccaccini, Lorenzo V.
    Chen, Hongli
    Ye, Minyou
    [J]. INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2016, 41 (17) : 7053 - 7058
  • [9] Neutronic analyses in support of the WCLL DEMO design development
    Moro, Fabio
    Del Nevo, Alessandro
    Flammini, Davide
    Martelli, Emanuela
    Mozzillo, Rocco
    Noce, Simone
    Villari, Rosaria
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 136 : 1260 - 1264
  • [10] Impact of neutronic constraints on the design and performance of a tokamak DEMO reactor
    Hong, B. G.
    [J]. FUSION ENGINEERING AND DESIGN, 2020, 155