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Nuclear Technology Volume 49, 1980 - Issue 3
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Technical Paper

Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Production

R. W. ConnUniversity of Wisconsin, Fusion Engineering Program Nuclear Engineering Department, Madison, Wisconsin 53706
,
F. KantrowitzUniversity of Wisconsin, Fusion Engineering Program Nuclear Engineering Department, Madison, Wisconsin 53706
&
W. F. VogelsangUniversity of Wisconsin, Fusion Engineering Program Nuclear Engineering Department, Madison, Wisconsin 53706
Pages 458-468 | Published online: 13 May 2017

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Selahaddin Orhan Akansu. (2007) Neutronic analysis of lithium hydride (LiH) material IN A (D, T) driven hybrid blanket. Journal of the Chinese Institute of Engineers 30:1, pages 1-10.
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Sebahattin Ünalan, S. Orhan Akansu & Hanifi Saraç. (2003) Improvement of the Inertial Fusion Energy Reactor Performance by Means of UF4 and ThF4. Fusion Science and Technology 43:2, pages 230-249.
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Sebahattin ÜNalan. (1998) Rejuvenation of the CANDU Spent Fuel in (D-T)–Driven Hybrid Reactors. Fusion Technology 33:4, pages 398-417.
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Sümer Şahin & Hüseyin Yapici. (1989) Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel. Fusion Technology 16:3, pages 331-345.
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Yoshiaki OKA, Takayasu KASAHARA & Shigehiro AN. (1985) Concept and Nuclear Performance of Direct-Enrichment Fusion Breeder Blanket Using UO2Powder. Journal of Nuclear Science and Technology 22:3, pages 165-173.
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