Three-dimensional neutronics assessment of dual coolant molten salt blankets with comparison to one-dimensional results

被引:11
|
作者
Sawan, ME
Youssef, MZ
机构
[1] Univ Wisconsin, Fus Technol Inst, Madison, WI 53706 USA
[2] Univ Calif Los Angeles, Los Angeles, CA 90095 USA
关键词
molten salt; 3-D neutronics; dual coolant; tritium breeding; nuclear heating; radiation damage;
D O I
10.1016/j.fusengdes.2005.08.082
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
Detailed three-dimensional (3-D) neutronics calculations have been performed for the dual coolant molten salt blanket designs. The model includes the detailed heterogeneous geometrical arrangement of the inboard (113) and outboard (013) blanket sectors. The total tritium breeding ratio (TBR) is similar to 1.07. The 1-D calculations tend to overestimate nuclear heating in the blanket by similar to 8% resulting in overestimating the plant thermal power. The approximate 1-D calculations overestimate damage and nuclear heating in the first wall (FW) and front zone of the blanket by factors of 1.3-1.7 but result in a steeper radial drop leading to significant underestimation (by up to a factor of 3) of nuclear parameters at the back. The 1-D calculations significantly underestimate radiation damage in the shield and vacuum vessel behind the blanket. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码:505 / 511
页数:7
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