DocumentCode
2114358
Title
Preliminary radiological assessment of the Fusion Ignition Research Experiment (FIRE)
Author
Khater, H.Y. ; Sawan, M.E.
Author_Institution
Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
fYear
1999
fDate
1999
Firstpage
475
Lastpage
478
Abstract
Detailed activation analysis has been performed for FIRE. The machine is assumed to have an operation schedule of 3000 D-T pulses with a pulse burn of 10 seconds and 2 hours between pulses. At shutdown, the decay heat induced in the first wall is less than 0.1% of the nuclear heating generated in the first wall during operation. The ratio between the shutdown decay heat and nuclear heating generated in the vacuum vessel during operation is on the order of 0.01%. At the end of the machine life, all components would qualify for disposal as Class C low level waste. The biological dose rates behind the vacuum vessel and the divertor remain high during the first year following shutdown. The biological dose rates behind the outboard magnet are acceptable only at locations where the vacuum vessel is more than 40 cm thick. Using a 30 cm thick POLY/CAST shield drops the dose rates on the top of the shield to acceptable levels within a week from shutdown
Keywords
dosimetry; fusion reactor theory; radioactive waste disposal; Class C low level waste; FIRE; Fusion Ignition Research Experiment; POLY/CAST; activation analysis; biological dose rate; decay heat; divertor; dose rate; nuclear heating; radiological; shutdown decay heat; vacuum vessel; Activation analysis; Coils; Fires; Heating; Ignition; Magnetic flux; Magnetic shielding; Neutrons; Nuclear power generation; Waste disposal;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1999. 18th Symposium on
Conference_Location
Albuquerque, NM
Print_ISBN
0-7803-5829-5
Type
conf
DOI
10.1109/FUSION.1999.849882
Filename
849882
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