Activation analysis and waste management for blanket materials of multi-functional experimental fusion-fission hybrid reactor (FDS-MFX)

被引:6
作者
Jiang, Jieqiong [1 ]
Yuan, Baoxin [1 ]
Zou, Jun [1 ]
Wu, Yican [1 ]
机构
[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Hefei 230031, Anhui, Peoples R China
关键词
Fusion; Fission; Hybrid; Multi-functional experimental reactor; Blanket; Activation; CONCEPTUAL DESIGN; MARTENSITIC STEEL; TRANSMUTATION; SYSTEM; PROGRESS; FUEL;
D O I
10.1016/j.fusengdes.2014.03.061
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
The preliminary studies of the activation analysis and waste management for blanket materials of the multi-functional experimental fusion fission hybrid reactor, i.e. Multi-Functional eXperimental Fusion Driven Subcritical system named FDS-MFX, were performed. The neutron flux of the FDS-MFX blanket was calculated using VisualBUS code and Hybrid Evaluated Nuclear Data Library (HENDL) developed by FDS Team. Based on these calculated neutron fluxes, the activation properties of blanket materials were analyzed by the induced radioactivity, the decay heat and the contact dose rate for different regions of the FDS-MFX blanket. The safety and environment assessment of fusion power (SEAFP) strategy, which was developed in Europe, was applied to FDS-MFX blanket for the management of activated materials. Accordingly, the classification and management strategy of activated materials after different cooling time were proposed for FDS-MFX blanket. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:405 / 411
页数:7
相关论文
共 41 条
[1]   AN ECONOMICS METHOD FOR SYMBIOTIC FUSION-FISSION ELECTRICITY-GENERATION SYSTEMS [J].
BERWALD, DH ;
MANISCALCO, JA .
NUCLEAR TECHNOLOGY-FUSION, 1981, 1 (01) :128-136
[2]   FUSION HYBRID [J].
BETHE, HA .
PHYSICS TODAY, 1979, 32 (05) :44-&
[3]   A high temperature blanket concept for hydrogen production [J].
Chen, H. ;
Wu, Y. ;
Konishi, S. ;
Hayward, Jim .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :903-911
[4]   MATERIALS RECYCLING CONSIDERATIONS FOR D-T FUSION-REACTORS [J].
CHENG, ET ;
SZE, DK ;
SOMMERS, JA ;
FARMER, OT .
FUSION TECHNOLOGY, 1992, 21 (03) :2001-2008
[5]   Prospect of nuclear waste transmutation and power production in fusion reactors [J].
Cheng, ET ;
Cerbone, RJ .
FUSION TECHNOLOGY, 1996, 30 (03) :1654-1658
[6]   VANADIUM RECYCLING [J].
DOLAN, TJ ;
BUTTERWORTH, GJ .
FUSION TECHNOLOGY, 1994, 26 (03) :1014-1020
[7]   Fusion solution to dispose of spent nuclear fuel, transuranic elements, and highly enriched uranium [J].
Gohar, Y .
FUSION ENGINEERING AND DESIGN, 2001, 58-59 :1097-1101
[8]   Progress in development of China Low Activation Martensitic Steel for fusion application [J].
Huang, Q. ;
Li, C. ;
Li, Y. ;
Chen, M. ;
Zhang, M. ;
Peng, L. ;
Zhu, Z. ;
Song, Y. ;
Gao, S. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 :142-146
[9]   Study of irradiation effects in China low activation martensitic steel CLAM [J].
Huang, QY ;
Li, JG ;
Chen, YX .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :268-272
[10]  
Jiang J., 2012, P PHYSOR 2012 ADV RE