A blanket concept with liquid Li17Pb83 for tritium breeding in INTOR-NET-Reference-Cited by-同舟云学术

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A blanket concept with liquid Li17Pb83 for tritium breeding in INTOR-NET

Published:1984-01 Issue:2 Volume:1 Page:185-194
ISSN:0167-899X
Container-title:Nuclear Engineering and Design. Fusion
language:en
Short-container-title:Nuclear Engineering and Design. Fusion

Author:

Airola J.,Biggio M.,Casini G.,Farfaletti-Casali F.,Li Bassi P.,Ponti C.,Rieger M.,Piana C.

Publisher

Elsevier BV

Subject

General Engineering

Reference11 articles.

1. Conceptual study of a lithium-lead eutectic blanket for a power reactor;Carré,1981

2. Demonstration Tokamak power plant;Abdou,1982

3. WITAMIR-I, a university of Wisconsin tandem mirror reactor design;Badger,1980

4. INTOR-Phase-I, IAEA,1982

5. INTOR-Phase-IIA, Critical Issues, Eur. Contr. to the INTOR-Phase-II Workshop,1982

Cited by 7 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. An innovative approach to effective breeding blanket design for future fusion reactors;Plasma Science and Technology;2024-10-01

2. Turbulence and the Feasibility of Self-Cooled Liquid Metal Blankets for Fusion Reactors;Fusion Technology;1986-11

3. Thermal release of tritium from neutron-irradiated Li7Pb2;Journal of the Less Common Metals;1986-05

4. Hydrogen solubility in liquid Li17Pb83;Journal of Nuclear Materials;1985-08

5. First Wall and Blanket Concepts for Experimental Fusion Reactors;Fusion Technology;1985-07

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