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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Toshiharu Takeishi, Kazunari Katayama, Masabumi Nishikawa, Naoyuki Miya, Kei Masaki
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 565-568
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A988
Articles are hosted by Taylor and Francis Online.
Tritium thermal release and full combustion with oxygen were performed on isotropic graphite tiles used for plasma facing material of JT-60U. Approximately 50-80 % of tritium was released by dry argon gas purge and 20-50 % of tritium was released by humid argon gas purge up to 800-1200 °C within one day, respectively. Further several percent of tritium was released by full combustion with oxygen. It was experimentally confirmed that all retained tritium is not released by thermal dry gas purge and by use of isotope exchange reaction at high temperature in such a short period. In the full combustion operation, isotropic graphite begins to combust at higher temperature than 650 °C, but effective combustion temperature was higher than 700 °C. Since it is very difficult to heat the graphite tile attached on the wall of vacuum vessel at higher than 700 °C, it is considered to be not easy to recover all the tritium retained in the graphite while in the vacuum vessel.
