2016年11月
Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO
FUSION ENGINEERING AND DESIGN
- 巻
- 109
- 号
- 開始ページ
- 1637
- 終了ページ
- 1643
- 記述言語
- 英語
- 掲載種別
- DOI
- 10.1016/j.fusengdes.2015.11.002
- 出版者・発行元
- ELSEVIER SCIENCE SA
The development of a water cooled ceramic breeder (WCCB) test blanket module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and development of DEMO blanket, R&D has been performed on the module fabrication technology, breeder and multiplier pebble fabrication technology, tritium production rate evaluation, as well as structural and safety design activities.
The fabrication of full-scale first wall, side walls, breeder pebble bed box and back wall was completed, and assembly of TBM with box structure was successfully achieved. Development of advanced breeder and multiplier pebbles for higher chemical stability was continued for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium transport simulation technology, investigation of the TBM neutron measurement technology and the evaluation of the tritium production and recovery test using D-T neutron in the fusion neutron source (FNS) facility has been performed. This paper provides an overview of the recent achievements of the development of the WCCB Blanket in Japan. (C) 2015 Elsevier B.V. All rights reserved.
The fabrication of full-scale first wall, side walls, breeder pebble bed box and back wall was completed, and assembly of TBM with box structure was successfully achieved. Development of advanced breeder and multiplier pebbles for higher chemical stability was continued for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium transport simulation technology, investigation of the TBM neutron measurement technology and the evaluation of the tritium production and recovery test using D-T neutron in the fusion neutron source (FNS) facility has been performed. This paper provides an overview of the recent achievements of the development of the WCCB Blanket in Japan. (C) 2015 Elsevier B.V. All rights reserved.
- リンク情報
-
- DOI
- https://doi.org/10.1016/j.fusengdes.2015.11.002
- Web of Science
- https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=JSTA_CEL&SrcApp=J_Gate_JST&DestLinkType=FullRecord&KeyUT=WOS:000382422100106&DestApp=WOS_CPL
- URL
- https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=84949523825&origin=inward
- ID情報
-
- DOI : 10.1016/j.fusengdes.2015.11.002
- ISSN : 0920-3796
- eISSN : 1873-7196
- SCOPUS ID : 84949523825
- Web of Science ID : WOS:000382422100106