Neutronic investigation of a hybrid version of the ARIES-RS fusion reactor

Annals of Nuclear Energy

Volumn 30, Issue 2, 2003, Pages 245-259

  Sahin, Sümer ^a   Yalçn, Senay ^b   Sahin, Hac Mehmet ^a   Übeyli, Mustafa ^a  

^a GAZI UNIVERSITY   (Turkey)

^b BAHCESEHIR UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDING BLANKETS; FISSION REACTIONS; NEUTRONS; NUCLEAR FUELS; NUCLEAR POWER PLANTS; POWER AMPLIFIERS;

FISSILE MATERIALS;

FUSION REACTORS;

TRITIUM;

EID: 0037208711     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(02)00049-X     Document Type: Article

References (27)

1. Prospects and issues for commercial fusion power systems
2. Overview of ARIES-RS neutronics and radiation shielding: Key issues and main conclusions
3. Long-term radioactivity in fusion reactors
4. Overview of ARIES-RS Tokamak fusion power plant
5. ARIES-RS safety design and analysis
6. Fission power flattening in hybrid blankets using mixed fuel
7. Power flattening in a catalyzed (D,D) fusion driven hybrid blanket using nuclear waste actinides
8. Potential of a catalyzed fusion driven hybrid reactor for the regeneration of CANDU spent fuel
9. Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket
10. Radiation damage in liquid-protected first wall materials for IFE-reactors
11. Radiation damage in liquid-protected first-wall materials for MFE-reactors
12. Rejuvenation of LWR spent fuel in fusion blankets
13. MFE-reactors with liquid protection for the first-wall
14. Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation
15. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel
16. Engineering design of the ARIES-RS power plant
17. Neutronic analysis of prometheus reactor fuelled with various compounds of thorium and uranium