Original language | English |
---|---|
Pages (from-to) | 1 |
Number of pages | 1 |
Journal | Fusion Engineering and Design |
Volume | 19 |
Issue number | 4 |
DOIs | |
Publication status | Published - 1992 Dec |
Externally published | Yes |
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
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Preface. / Akiyama, Mamoru; Takagi, Toshiyuki.
In: Fusion Engineering and Design, Vol. 19, No. 4, 12.1992, p. 1.Research output: Contribution to journal › Editorial › peer-review
}
TY - JOUR
T1 - Preface
AU - Akiyama, Mamoru
AU - Takagi, Toshiyuki
N1 - Funding Information: In nuclear fusion research performed in large tokamak facilities like JT-60, JET and TFTR recently remarkable progress is accomplished concerning the plasma parameters for the break-even condition region and the research is now moving to the next step towards an experimental reactor, the International Thermonuclear Experimental Reactor (ITER). ITER will be the first device that is recognizable as a nuclear system. Nuclear fusion technology such as the technology concerning the high heat flux component, magnetomechanics, materials, neutronics, tritium, and blanket, will play a very important role in the research and development for the experimental reactor as well as for the future power reactor. This special issue contains papers related to thermal and mechanical problems, which are important areas of fusion reactor technology. The research in these papers was performed as a fundamental and systematic research project by a blanket thermal and mechanical research group in Japan. The group was financially supported by a Grant-in-Aid for Fusion Research of the Ministry of Education, Science and Culture in Japan. The group has performed basic research on the structural and thermal design of the first wall and the blanket in the magnetic fusion reactor. The theoretical and experimental research topics in the group were as follows: (1) Studies on abnormal phenomena appearing in the first wall after plasma disruption, such as melting and resolidification, crack generation and growth, lifetime prediction of the wall, etc. (2) Electromagnetics in the first wall, such as eddy current, dynamic deformation due to Lorentz forces, magnetosolid mechanics, flaw detection, etc. (3) New heat-removal concepts for the first wall and blanket, using gas, water, liquid metal, two-phase flow, etc. (4) Material strength studies on carbon, structural material, composite material, etc. With respect to the results achieved by the group, this issue includes eight papers concerning the behavior of the first wall after plasma disruption, problems on a new heat-removal concept of the first wall, material strength, and numerical methodology for solving the convective diffusion equation. The contributors to this issue are gratefully acknowledged as well as persons who helped in the realization of the publication.
PY - 1992/12
Y1 - 1992/12
UR - http://www.scopus.com/inward/record.url?scp=44049109355&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=44049109355&partnerID=8YFLogxK
U2 - 10.1016/0920-3796(92)90001-K
DO - 10.1016/0920-3796(92)90001-K
M3 - Editorial
AN - SCOPUS:44049109355
VL - 19
SP - 1
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 4
ER -