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Publicatie Laka-bibliotheek:
Technology Assessment HTR; 5 - Thorium Fueled High Temperature gas cooled Reactors (1996)

AuteurECN, Bultman
Datumjuni 1996
Classificatie 6.01.3.51/11 (VEILIGHEID - REACTOREN - NIEUWE GENERATIES - HTR)
Voorkant

Uit de publicatie:

SUMMARY

Thorium as a fertile fuel component for the High Temperature Gascooled Reactor 
(HTR) instead of uranium has been reviewed. The use of thorium is generally 
believed to be more in agreement with philosophies of sustainability, low actinide 
waste production, and non-proliferation. The HTR is considered because of the 
inherent safety features, which excludes fuel melting due to decay heat during loss 
of coolant accidents.
It has been concluded that the use of thorium might be beneficial to reduce the 
actinide waste production. Preferably, uranium has to be recycled and extra fissile 
material has to be used in the form of highly-enriched uranium. This is in 
contradiction with the current doctrines of non-proliferation, although the safeguard 
ability of highly-enriched uranium is generally accepted to be possible.

A self-sustaining fuel cycle might be possible in the HTR, but this could reduce the 
inherent safety features of the design and it could lead to higher proliferation risks 
and fuel cycle costs. To obtain breeding in an HTR, a larger core size is necessary, 
which will reduce the passive cooling capabilities. The higher proliferation risks a
re due to the occurrence of the fissile U-233 in the fuel cycle. This can be prevented 
by diluting this fissile material with U-238, but this will change the thorium fuel 
cycle slowly into a fuel cycle containing mainly U-238 instead of Th-232.

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