DocumentCode
300953
Title
Fusion safety experiments in JAERI
Author
Kunugi, T. ; Takase, K. ; Ogawa, M. ; Seki, Y.
Author_Institution
JAERI, Ibaraki, Japan
Volume
1
fYear
1995
fDate
30 Sep-5 Oct 1995
Firstpage
313
Abstract
Two experimental studies for the thermal-hydraulic safety of fusion reactors, ingress of the coolant events (ICE) and loss of vacuum events (LOVA), have been started as ITER safety sub-tasks for three years since February, 1995. In these researches, as for the ICE experiments, the preliminary ICE apparatus has been completed by the end of September, 1995. On the other hand, as for the LOVA experiments, the preliminary LOVA apparatus that simulated a vacuum vessel of the fusion reactor with a small-scaled model has already been constructed. The buoyancy-driven exchange flow behavior through breaches between the inside (filled with helium gas) and the outside (i.e., air) of the apparatus under the LOVA condition was investigated quantitatively. This paper summarizes the outline of the preliminary ICE and LOVA apparatuses, their experimental contents and research schedules
Keywords
Tokamak devices; fusion reactor safety; plasma toroidal confinement; ICE; ITER safety sub-tasks; JAERI; LOVA; buoyancy-driven exchange flow behavior; fusion safety experiments; ingress of the coolant events; loss of vacuum events; thermal-hydraulic safety; vacuum vessel; Heat transfer; Ice; Plasma materials processing; Plasma measurements; Plasma temperature; Plasma waves; Pressure measurement; Safety; Size measurement; Water heating;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location
Champaign, IL
Print_ISBN
0-7803-2969-4
Type
conf
DOI
10.1109/FUSION.1995.534230
Filename
534230
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