Preliminary Shielding Design and Analysis of Liquid Lead-Lithium Blanket for Chinese Fusion Engineering Testing Reactor

被引：2
|
作者：
Sun, Guangyao [1 ,2 ]
Lian, Chao [2 ]
Ni, Muyi [2 ]
Song, Jing [2 ]
Wang, Minghuang [2 ]
Jiang, Jieqiong [2 ]
Hu, Liqin [1 ,2 ]
机构：
[1] Univ Sci & Technol China, Hefei 230026, Anhui, Peoples R China
[2] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
来源：
JOURNAL OF FUSION ENERGY | 2015年 / 34卷 / 02期
关键词：
CFETR; Lead-lithium; Blanket; Shielding design; SuperMC; RESEARCH-AND-DEVELOPMENT; CONCEPTUAL DESIGN; NEUTRONICS ANALYSIS; ITER; FDS; TECHNOLOGY; STRATEGY; SYSTEMS; MODULE;
D O I：
10.1007/s10894-014-9819-x
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：
To fill the gap between ITER and fusion DEMO plant, the conceptual design of Chinese Fusion Engineering Testing Reactor (CFETR) has been proposed. In this study, the shielding blanket of liquid lead-lithium blanket for CFETR was designed with newly-developed three dimensional (3D) models. The detailed shielding scheme was obtained with the 3D CFETR model to optimize the shielding parameters such as the shielding material and size, by using the Super Monte Carlo Simulation Program for Nuclear and Radiation Process. The radiation limits of fast neutron flux and nuclear heating density in the Toroidal Field Coils were considered and with the nuclear analysis for the 3D model, the obtained shielding scheme could meet the requirement of radiation limits.
引用
收藏
页码：443 / 447
页数：5
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