NEUTRONICS ANALYSIS FOR AQUEOUS SELF-COOLED FUSION REACTOR BLANKETS.

被引：0

作者：

Embrechts, M.J. ^{[1
]}

Varsamis, G. ^{[1
]}

Jaffa, R. ^{[1
]}

Steiner, D. ^{[1
]}

Deutsch, L. ^{[1
]}

Gierszewski, P. ^{[1
]}

机构：

[1] Renssalaer Polytechnic Inst, Troy,, NY, USA, Renssalaer Polytechnic Inst, Troy, NY, USA

来源：

Fusion Technology | 1986年 / 10卷 / 3 pt 2B期

关键词：

TOKAMAK DEVICES - Research;

D O I：

10.13182/fst86-a24937

中图分类号：

学科分类号：

摘要：

The tritium breeding performance of several Aqueous Self-Cooled Blanket (ASCB) configurations for fusion reactors has been evaluated. The tritium breeding performance of an ASCB for a MARS-like-tandem mirror reactor and an ASCB based breeding-shield for the next European Torus (NET) are assessed here. Two design options for the MARS-like blanket are discussed and it is demonstrated that both design options lead to low-activation blankets that allow class burial.

引用

页码：1443 / 1448