Neutronics analysis of the conceptual design of a component test facility based on the spherical tokamak

被引:2
作者
Zheng, S. [1 ]
Voss, G. M. [1 ]
Pampin, R. [1 ]
机构
[1] CCFE Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
Neutronics; CTF; Spherical tokamak; Fusion; COPPER-ALLOYS; TEMPERATURE; IRRADIATION;
D O I
10.1016/j.fusengdes.2010.09.009
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
One of the crucial aspects of fusion research is the optimisation and qualification of suitable materials and components. To enable the design and construction of DEMO in the future, ITER is taken to demonstrate the scientific and technological feasibility and IFMIF will provide rigorous testing of small material samples. Meanwhile, a dedicated, small-scale components testing facility (CTF) is proposed to complement and extend the functions of ITER and IFMIF and operate in association with DEMO so as to reduce the risk of delays during this phase of fusion power development. The design of a spherical tokamak (ST)-based CTF is being developed which offers many advantages over conventional machines, including lower tritium consumption, easier maintenance, and a compact assembly. The neutronics analysis of this system is presented here. Based on a three-dimensional neutronics model generated by the interface programme MCAM from CAD models, a series of nuclear and radiation protection analyses were carried out using the MCNP code and FENDL2.1 nuclear data library to assess the current design and guide its development if needed. The nuclear analyses addresses key neutronics issues such as the neutron wall loading (NWL) profile, nuclear heat loads, and radiation damage to the coil insulation and to structural components, particularly the stainless steel vessel wall close to the NBI ports where shielding is limited. The shielding of the divertor coil and the internal Poloidal Field (PF) coil, which is introduced in the expanded divertor design, are optimised to reduce their radiation damage. The preliminary results show that the peak radiation damage to the structure of martensitic/ferritic steel is about 29 dpa at the mid-plane assuming a life of 12 years at a duty factor 33%, which is much lower than its similar to 150 dpa limit. In addition, TBMs installed in 8 mid-plane ports and 6 lower ports, and 60% Li-6 enrichment in the Li4SiO4 breeder, the total tritium generation is similar to 3.7 kg in the whole lifetime of CTF. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:2300 / 2304
页数:5
相关论文
共 15 条
  • [1] [Anonymous], 2003, MCNP5 MAN MCNP GEN M
  • [2] [Anonymous], G73DDD2W02 ITER
  • [3] EDWARDS DJ, 1992, J NUCL MATER A, V191, P416
  • [4] Overview of ARIES-RS neutronics and radiation shielding: key issues and main conclusions
    El-Guebaly, LA
    [J]. FUSION ENGINEERING AND DESIGN, 1997, 38 (1-2) : 139 - 158
  • [5] Low-temperature radiation embrittlement of copper alloys
    Fabritsiev, SA
    Pokrovsky, AS
    Zinkle, SJ
    Edwards, DJ
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 513 - 518
  • [6] The effect of neutron dose, irradiation and testing temperature on mechanical properties of copper alloys
    Fabritsiev, SA
    Pokrovsky, AS
    Edwards, DJ
    Zinkle, SJ
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 1015 - 1021
  • [7] Benchmarking of MCAM 4.0 with the ITER 3D model
    Li, Y.
    Lu, L.
    Ding, A.
    Hu, H.
    Zeng, Q.
    Zheng, S.
    Wu, Y.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2861 - 2866
  • [8] Lopez Al-dama D., 2004, INDCNDS46 IAEA
  • [9] Lu L., 7308 ITER ITA
  • [10] Valenza D., NAG26160497 ITER