DocumentCode :
3170296
Title :
Safety in the ARIES-III D3He tokamak reactor design
Author :
Herring, J. Stephen ; Dolan, Thomas J.
Author_Institution :
EG&G Idaho Inc., Idaho Falls, ID, USA
fYear :
1991
fDate :
30 Sep-3 Oct 1991
Firstpage :
708
Abstract :
The ARIES-III reactor study is an extensive examination of the viability of a D-3He commercial tokamak power reactor. The ARIES-III reactor uses an organic coolant to cool the first wall, shield and divertor. The authors explored the potential for isotopically tailoring the 4-mm tungsten layer on the divertor in order to reduce the offsite doses should a tungsten aerosol be released from the reactor after an accident. They also modeled a loss-of-cooling accident in which the organic coolant was burning in order to estimate the amount of radionuclides released from the first wall. Because the maximum temperature is low, <600°C, release fractions are small. The authors analyzed the disposition of the 20 g/day of tritium that is produced by D-D reactions and removed by the vacuum pumps. The results reemphasize the need for low activation materials and advanced divertor designs, even in reactors using advanced fuels
Keywords :
Tokamak devices; accidents; fusion reactor materials; fusion reactor safety; fusion reactor theory and design; radiation protection; ARIES-III reactor; D-D reactions; D3He tokamak reactor design; T; advanced divertor designs; advanced fuels; commercial tokamak power reactor; divertor; first wall; loss-of-cooling accident; low activation materials; offsite doses; organic coolant; radionuclides; shield; Accidents; Aerosols; Coolants; Fuels; Helium; Inductors; Safety; Temperature; Tokamaks; Tungsten;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
Type :
conf
DOI :
10.1109/FUSION.1991.218750
Filename :
218750
Link To Document :
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