DocumentCode
2027944
Title
Safety analysis of potential loss of vacuum incident in JET
Author
Wykes, M.E.P.
Author_Institution
JET Joint Undertaking, Abingdon, UK
fYear
1989
fDate
2-6 Oct 1989
Firstpage
312
Lastpage
315
Abstract
During plasma discharges, the graphite first-wall tiles of the JET (Joint European Torus) will be subjected to high thermal fluxes and consequent high temperatures. Accidental loss of vacuum through air inleakage in such a situation could cause graphite oxidation and concomitant energy input to the inleaking gas. The JET Exhaust Detritiation System (EDS) is designed to prevent the escape of tritiated gases and activated or toxic dust from the torus by pumping the breached torus to maintain a slightly subatmospheric pressure. A safety analysis is presented to verify that the design pumping capacity of the EDS is adequate to address the peak graphite oxidation rates envisaged during a potential air inleakage incident with hot graphite in the JET
Keywords
accidents; fusion reactor materials; fusion reactor safety; graphite; plasma confinement; tritium handling; Exhaust Detritiation System; JET; Joint European Torus; concomitant energy input; design pumping capacity; graphite first-wall tiles; graphite oxidation; high thermal fluxes; plasma discharges; potential loss of vacuum incident; safety analysis; toxic dust; tritiated gases; Air safety; Elementary particle vacuum; Gases; Heat transfer; Helium; Oxidation; Plasma temperature; Protection; Tiles; Upper bound;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102229
Filename
102229
Link To Document