Innovative Liquid Breeder Blanket Design Activities in Japan

Journal Article · Fri Apr 15 00:00:00 EDT 2005 · Fusion Science and Technology

DOI:https://doi.org/10.13182/FST47-524· OSTI ID:20849916

Sagara, Akio ^[1]; Tanaka, Teruya ^[1]; Muroga, Takeo ^[1]; Hashizume, Hidetoshi ^[2]; Kunugi, Tomoaki ^[3]; Fukada, Satoshi ^[4]; Shimizu, Akihiko ^[4]

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1. National Institute for Fusion Science (Japan)
2. Tohoku University (Japan)
3. Kyoto University (Japan)
4. Kyushu University (Japan)

In order to clarify key engineering issues and to enhance key R and D activities for D-T fusion blankets, many design activities on innovative liquid blanket systems are on going as collaboration studies in Japan. Recently an improved long-life Flibe blanket has been proposed, and the self-cooled Li/V blanket design has started. For Flibe systems, much progress has been made on tritium permeation barrier, energy conversion system, free surface designs, and thermofluid loop experiments. For Li/V systems, evaluation studies have proceeded on Be-free nuclear properties and allowable crack fraction on multilayered MHD insulation coatings.

• OSTI ID: 20849916
• Journal Information: Fusion Science and Technology, Vol. 47, Issue 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
COATINGS
CRACKS
D-T OPERATION
DESIGN
ENERGY CONVERSION
ENGINEERING
EVALUATION
FLIBE
JAPAN
LIQUIDS
MAGNETOHYDRODYNAMICS
NUCLEAR PROPERTIES
SURFACES
TRITIUM