Fusion Safety Research and Development in JAERI |
| |
Authors: | Tomoaki Kunugi Yasushi Seki |
| |
Affiliation: | (1) Department of Reactor Engineering, Japan Atomic Energy Research Institute, Tokai-mura, Naka, Ibaraki, 319-11, Japan;(2) Department of Fusion Engineering, Japan Atomic Energy Research Institute, Naka-machi, Naka, Ibaraki, 311-01, Japan |
| |
Abstract: | This paper describes the current status and future plans of the fusion safety research and development regarding to the developments of the dust removal system and safety analysis code and the thermofluid experiments in the Japan Atomic Energy Research Institute (JAERI) for a fusion experimental reactor. The containment of the radioactive material is the key to achieve fusion safety. In the event of accidents, the source terms need to be evaluated with sufficient accuracy. Therefore, in JAERI, the dust characterization have been investigated and the dust removal system using electric force has been developed and tested. A safety analysis code including both thermal and plasma transient analyses under the various event sequences has been developed. Moreover, the preliminary experiments of thermofluid transients in the vacuum vessel such as Ingress of Coolant Event (ICE) and Loss of Vacuum Event (LOVA) have been started and the experimental results using preliminary LOVA/ICE apparatus during 1995–1996 are summarized in this paper. |
| |
Keywords: | Fusion safety R& D dust removal system safety analysis code ingress of coolant event (ICE) loss of vacuum event (LOVA) |
本文献已被 SpringerLink 等数据库收录! |
|