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Volumn 34, Issue 2, 1998, Pages 109-127

Improvement of the neutronic performance of the hybrid reactor rejuvenating spent fuels using various moderators

Author keywords

Hybrid blankets; Rejuvenation; Spent fuel

Indexed keywords

BERYLLIUM; BREEDER REACTORS; BREEDING BLANKETS; CARBON; HEAVY WATER; MELTING; MODERATORS; NUCLEAR ENERGY; NUCLEAR FUEL REPROCESSING; RADIATION DAMAGE; SPENT FUELS; TRITIUM;

EID: 0032165509     PISSN: 07481896     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST98-A57     Document Type: Article
Times cited : (6)

References (20)
  • 1
    • 0021177650 scopus 로고
    • Fusion-Fission Hybrid Reactors
    • J. LEWINS and M. BECKER, Eds., Plenum Press
    • E. GREENSPAN, "Fusion-Fission Hybrid Reactors," Advances in Nuclear Science and Technology, Vol. 16, p. 289, J. LEWINS and M. BECKER, Eds., Plenum Press (1984).
    • (1984) Advances in Nuclear Science and Technology , vol.16 , pp. 289
    • Greenspan, E.1
  • 2
    • 0003252208 scopus 로고
    • Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Production,"
    • R. W. CONN, F. KANTROWITZ, and W. F. VOGELSANG, "Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Production," Nucl. Technol, 49, 458 (1980).
    • (1980) Nucl. Technol , vol.49 , pp. 458
    • Conn, R.W.1    Kantrowitz, F.2    Vogelsang, W.F.3
  • 4
    • 0038608704 scopus 로고
    • A Numerical-Graphical Power Flattening Method for Fast Hybrid Blankets
    • Madrid, Spain, June 30-July 4, 1986
    • S. ŞAHIN and M. AL-ESHAIKH, "A Numerical-Graphical Power Flattening Method for Fast Hybrid Blankets," Proc. 4th Int. Conf. Emerging Nuclear Energy Systems, Madrid, Spain, June 30-July 4, 1986, p. 59 (1986).
    • (1986) Proc. 4th Int. Conf. Emerging Nuclear Energy Systems , pp. 59
    • Şahin, S.1    Al-Eshaikh, M.2
  • 5
    • 0023450506 scopus 로고
    • Fission Power Flattening in Hybrid Reactors Using Mixed Fuel
    • S. ŞAHIN and M. AL-ESHAIKH, "Fission Power Flattening in Hybrid Reactors Using Mixed Fuel," Fusion Technol, 12, 395 (1987).
    • (1987) Fusion Technol , vol.12 , pp. 395
    • Şahin, S.1    Al-Eshaikh, M.2
  • 6
    • 0039047138 scopus 로고
    • A Fast Hybrid Blanket with Flat Fusion Power over a Long Operational Period
    • S. ŞAHIN, A. ERISEN, and Y. ÇEBI, "A Fast Hybrid Blanket with Flat Fusion Power over a Long Operational Period," Trans. Am. Nucl. Soc., 54, 134 (1987).
    • (1987) Trans. Am. Nucl. Soc. , vol.54 , pp. 134
    • Şahin, S.1    Erisen, A.2    Çebi, Y.3
  • 7
    • 0024305136 scopus 로고
    • Realization of a Flat Fission Power Density in a Hybrid Blanket over Long Operation Periods
    • S. ŞAHIN, A. ERIŞEN, and Y. ÇEBI, "Realization of a Flat Fission Power Density in a Hybrid Blanket over Long Operation Periods," Fusion Technol., 15, 37 (1989).
    • (1989) Fusion Technol , vol.15 , pp. 37
    • Şahin, S.1    Erişen, A.2    Çebi, Y.3
  • 8
    • 0025497858 scopus 로고
    • Power Flattening in a Catalyzed Deuterium-Deuterium Fusion Driven Hybrid Blanket Using Nuclear Waste Actinides
    • S. ŞAHIN, "Power Flattening in a Catalyzed Deuterium-Deuterium Fusion Driven Hybrid Blanket Using Nuclear Waste Actinides," Nucl. Technol., 92, 93 (1990).
    • (1990) Nucl. Technol. , vol.92 , pp. 93
    • Şahin, S.1
  • 9
    • 0000404855 scopus 로고
    • Rejuvenation of CANDU Spent Fuel in a Hybrid Blanket
    • S. ŞAHIN and H. YAPICI, "Rejuvenation of CANDU Spent Fuel in a Hybrid Blanket," Trans. Am. Nucl. Soc., 59, 105 (1989).
    • (1989) Trans. Am. Nucl. Soc. , vol.59 , pp. 105
    • Şahin, S.1    Yapici, H.2
  • 10
    • 0024769818 scopus 로고
    • Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel
    • S. ŞAHIN and H. YAPICI, "Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel," Fusion Technol., 16, 331 (1989).
    • (1989) Fusion Technol , vol.16 , pp. 331
    • Şahin, S.1    Yapici, H.2
  • 11
    • 0040825611 scopus 로고
    • Heavy Water Reactor Spent-Fuel Regeneration with Fusion Neutrons
    • S. ŞAHIN, H. YAPICI, and E. BALTACIOǦLU, "Heavy Water Reactor Spent-Fuel Regeneration with Fusion Neutrons," Trans. Am. Nucl. Soc., 60, 176 (1989).
    • (1989) Trans. Am. Nucl. Soc. , vol.60 , pp. 176
    • Şahin, S.1    Yapici, H.2    Baltacioǧlu, E.3
  • 12
    • 0026202353 scopus 로고
    • Potential of a Catalyzed Fusion Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel
    • S. ŞAHIN, E. BALTACIOǦLU, and H. YAPICI, "Potential of a Catalyzed Fusion Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel," Fusion Technol., 20, 26 (1991).
    • (1991) Fusion Technol , vol.20 , pp. 26
    • Şahin, S.1    Baltacioǧlu, E.2    Yapici, H.3
  • 13
    • 0001953960 scopus 로고
    • Rejuvenation of LWR Spent Fuel in a Catalyzed Fusion Hybrid Blanket
    • S. ŞAHIN, H. YAPICI, and E. BALTACIOǦLU, "Rejuvenation of LWR Spent Fuel in a Catalyzed Fusion Hybrid Blanket," Kerntechnik, 59, 6, 243 (1994).
    • (1994) Kerntechnik , vol.59 , Issue.6 , pp. 243
    • Şahin, S.1    Yapici, H.2    Baltacioǧlu, E.3
  • 14
    • 0032114998 scopus 로고    scopus 로고
    • Rejuvenation of the CANDU Spent Fuel in (D-T)-Driven Hybrid Reactors
    • S. ÜNALAN, "Rejuvenation of the CANDU Spent Fuel in (D-T)-Driven Hybrid Reactors," Fusion Technol., 33, 398 (1998).
    • (1998) Fusion Technol , vol.33 , pp. 398
    • Ünalan, S.1
  • 17
    • 0001858160 scopus 로고
    • CLAWIV, Coupled 30 Neutrons, 12 Gamma Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations
    • Oak Ridge National Laboratory May
    • T. A. AL-KUSAYER, S. ŞAHIN, and A. DRIRA, "CLAWIV, Coupled 30 Neutrons, 12 Gamma Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations," RSIC Newslett., p. 4, Oak Ridge National Laboratory (May 1988).
    • (1988) RSIC Newslett , pp. 4
    • Al-Kusayer, T.A.1    Şahin, S.2    Drira, A.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.