Dynamic tritium inventory of a NET/ITER fuel cycle with lithium salt solution blanket-Reference-Cited by-同舟云学术

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Dynamic tritium inventory of a NET/ITER fuel cycle with lithium salt solution blanket

Published:1991-12 Issue: Volume:17 Page:271-277
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Spannagel Gert,Gierszewski Paul

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference11 articles.

1. A self-cooled heavy-water breeding blanket;Steiner,1985

2. Potential and problems of an aqueous lithium salt solution blanket for NET;Küchle,1987

3. Preliminary design of a tritium recovery system for an aqueous lithium salt blanket on NET;Galky;CFFTP report, CFFTP-G-8903,1989

4. Modeling and simulation of tritium handling systems;Gabowitsch;Kerntechnik,1989

5. Breeding ratio, inventory and doubling time in a D-T fusion reactor;Vogelsang;Nuclear Technology,1972

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