Neutron irradiation effects on the ITER-EDA and ITER-RC first wall/blanket materials

被引：0
|
作者：
Cambi, G [1 ]
Cepraga, DG [1 ]
Frisoni, M [1 ]
Carloni, F [1 ]
机构：
[1] Univ Bologna, Dept Phys, I-40126 Bologna, Italy
来源：
18TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING | 1999年
关键词：
D O I：
10.1109/FUSION.1999.849850
中图分类号：
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号：
0807 ; 0820 ;
摘要：
Safety relevant effects of the neutron irradiation (material activation, decay heat, radiation damage, heat deposition and gas production) on the in-vessel components materials of the ITER-EDA and the preliminary European ITER-RC designs are assessed. The integrated radiation transport and activation methodological approach based on the calculation sequence Vitamin(ENEA)-Scale-ANITA has been used. The first wall and shield blanket FW/SB are water cooled and the structural material is AISI 316LN with Beryllium as protective layer material.
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页码：330 / 333
页数：4
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