Neutronic analysis of a moderated (D, T) fusion driven hybrid blanket

Annals of Nuclear Energy

Volumn 27, Issue 13, 2000, Pages 1237-1244

  Yapici, Hüseyin ^a   Akansu, S Orhan ^a   Özceyhan, Veysel ^a  

^a ERCIYES UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; DEUTERIUM; FUSION REACTIONS; LITHIUM; LITHIUM COMPOUNDS; NUCLEAR FUELS; PLUTONIUM; THORIA; TRITIUM; URANIUM DIOXIDE;

FLIBE; FUSION DRIVEN HYBRID BLANKETS;

BREEDING BLANKETS;

EID: 0033737352     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00122-X     Document Type: Article

References (10)

1. Conn R.W., Kantrowitz K., Vogelsang W.F. Hybrids for direct enrichment and self-protected fissile fuel production. Nuclear Technology. 49:1980;458.
2. Greenspan, E., 1984. Fusion-fission hybrid reactors. In: Lewins, J., Becker, M. (Eds.), Advances in Nuclear Science and Technology. Plenum Press, New York, Vol. 16.
3. Maniscalo J.A., Moir R.W. Recent progress in fusion-fission (hybrid) reactor design studies. Nuclear Technology/Fusion. 4:1981;419.
4. Meyer W., Loyalka S.K., Nelson W.E., Williams R.W. The homemade nuclear bomb syndrome. Nucl. Safety. 18:1977;427.
5. Şahin S. Reply to Remarks on the plutonium-240 induced pre-ignition problem in a nuclear device. Nucl. Technol. 54:1980;431.
6. Şahin S., Ligou J. The effect of the spontaneous fission of plutonium-240 on the energy release in a nuclear explosive. Nucl. Technol. 50:1980;88.
7. Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver. Fusion Technology. 10:1986;84.
8. Şahin S., Yapici H. Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel. Fusion Technology. 16:1989;331.
9. Şahin S., Yapici H., Baltacioǧlu E. Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket. Kerntechnik. 59:1994;243.
10. Yapici H., Çürüttü İ., Özceyhan V., Kirbiyik M. Potential of a fusion-fission hybrid reactor using various coolants to breed fissile fuel for LWRs. Annals of Nuclear Energy. 26:1999;821.