The helium-cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentation

被引：12
|
作者：
Li Puma, A [1 ]
Poitevin, Y [1 ]
Giancarli, L [1 ]
Rampal, G [1 ]
Farabolini, W [1 ]
机构：
[1] CEA Saclay, F-91191 Paris, France
来源：
FUSION ENGINEERING AND DESIGN | 2005年 / 75-79卷
基金：
欧盟地平线“2020”;
关键词：
HCLL; test blanket module; test sequence in ITER;
D O I：
10.1016/j.fusengdes.2005.06.132
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：
In this paper, a preliminary testing program is proposed to test and validate the helium-cooled lithium lead breeder blanket concept in the ITER machine. The proposal envisages four different test mock-ups or modules, adapted for qualifying single or combined effects and whose design makes large use of engineering scaling for compensating the differences between the testing conditions and those expected in DEMO (e.g., neutron wall load, heat flux, pulsed operating conditions). (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码：951 / 955
页数：5
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