메뉴 건너뛰기




Volumn 44, Issue 16, 2003, Pages 2567-2587

Light and heavy water cooled hybrid reactors for rejuvenation of LWR spent fuels

Author keywords

Hybrid reactors; LWR spent fuel; Rejuvenation; Water coolant

Indexed keywords

FUSION REACTIONS; LIGHT WATER REACTORS; PLASMAS; SPENT FUELS; VOLUME FRACTION;

EID: 0038713375     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0196-8904(03)00018-9     Document Type: Article
Times cited : (12)

References (37)
  • 1
    • 0003252208 scopus 로고
    • Hybrids for direct enrichment and self-protected fissile fuel production
    • Conn R.W., Kantrowitz F., Vogelsang F. Hybrids for direct enrichment and self-protected fissile fuel production. Nucl. Technol. 49:1980;458.
    • (1980) Nucl. Technol. , vol.49 , pp. 458
    • Conn, R.W.1    Kantrowitz, F.2    Vogelsang, F.3
  • 3
    • 0021177650 scopus 로고
    • Fusion-fission hybrid reactors
    • J. Lewins, & M. Becker. New York: Plenum Press
    • Greenspan E. Fusion-fission hybrid reactors. Lewins J., Becker M. Advances in Nuclear Science and Technology. vol. 16:1984;Plenum Press, New York.
    • (1984) Advances in Nuclear Science and Technology , vol.16
    • Greenspan, E.1
  • 4
    • 0019621466 scopus 로고
    • Power density flattening in fission-fusion hybrid reactors
    • Ericson K., McCormiick N.J., Woodruff G.L. Power density flattening in fission-fusion hybrid reactors. Nucl. Technol. 1:1981;533.
    • (1981) Nucl. Technol. , vol.1 , pp. 533
    • Ericson, K.1    McCormiick, N.J.2    Woodruff, G.L.3
  • 5
    • 0020751846 scopus 로고
    • Power density flattening in fission-fusion hybrid reactors
    • Greenspan E., Misulovin A., Gila D. Power density flattening in fission-fusion hybrid reactors. Nucl. Technol. 3:1983;485.
    • (1983) Nucl. Technol. , vol.3 , pp. 485
    • Greenspan, E.1    Misulovin, A.2    Gila, D.3
  • 7
    • 0023450506 scopus 로고
    • Fission power flattening in hybrid reactors using mixed fuel
    • Şahin S., Al-Eshaikh M. Fission power flattening in hybrid reactors using mixed fuel. Fusion Technol. 12:1987;395.
    • (1987) Fusion Technol. , vol.12 , pp. 395
    • Şahin, S.1    Al-Eshaikh, M.2
  • 8
    • 0024305136 scopus 로고
    • Realization of a flat fission power density in a hybrid blanket over long operation periods
    • Şahin S., Erişen A., Çebi Y. Realization of a flat fission power density in a hybrid blanket over long operation periods. Fusion Technol. 15:1989;37.
    • (1989) Fusion Technol. , vol.15 , pp. 37
    • Şahin, S.1    Erişen, A.2    Çebi, Y.3
  • 9
    • 0025497858 scopus 로고
    • Power flattening in a catalyzed deuterium-deuterium fusion driven hybrid blanket using nuclear waste actinides
    • Şahin S. Power flattening in a catalyzed deuterium-deuterium fusion driven hybrid blanket using nuclear waste actinides. Nucl. Technol. 92:1990;93.
    • (1990) Nucl. Technol. , vol.92 , pp. 93
    • Şahin, S.1
  • 10
    • 0024769818 scopus 로고
    • Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel
    • Şahin S., Yapici H. Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel. Fusion Technol. 16:1989;331.
    • (1989) Fusion Technol. , vol.16 , pp. 331
    • Şahin, S.1    Yapici, H.2
  • 11
    • 0026202353 scopus 로고
    • Potential of a catalyzed fusion driven hybrid reactor for the regeneration of CANDU spent fuel
    • Şahin S., Baltacioglu E., Yapici H. Potential of a catalyzed fusion driven hybrid reactor for the regeneration of CANDU spent fuel. Fusion Technol. 20:1991;26.
    • (1991) Fusion Technol. , vol.20 , pp. 26
    • Şahin, S.1    Baltacioglu, E.2    Yapici, H.3
  • 12
    • 0001953960 scopus 로고
    • Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket
    • Şahin S., Yapici H., Baltacioglu E. Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket. Kerntechnik. 59(6):1994;243-277.
    • (1994) Kerntechnik , vol.59 , Issue.6 , pp. 243-277
    • Şahin, S.1    Yapici, H.2    Baltacioglu, E.3
  • 13
    • 0032114998 scopus 로고    scopus 로고
    • Rejuvenation of CANDU spent fuel in (D-T)-driven hybrid reactors
    • Ünalan S. Rejuvenation of CANDU spent fuel in (D-T)-driven hybrid reactors. Fusion Technol. 33:1998;398.
    • (1998) Fusion Technol. , vol.33 , pp. 398
    • Ünalan, S.1
  • 14
    • 0031998295 scopus 로고    scopus 로고
    • Rejuvenation of LWR spent fuel in (D-T)-driven hybrid reactors
    • Ünalan S. Rejuvenation of LWR spent fuel in (D-T)-driven hybrid reactors. Fusion Eng. Des. 38:1998;393.
    • (1998) Fusion Eng. Des. , vol.38 , pp. 393
    • Ünalan, S.1
  • 15
    • 0032165509 scopus 로고    scopus 로고
    • Improvement of the neutronic performance of the hybrid reactor rejuvenating spent fuels using various moderators
    • Ünalan S., Akansu S.O. Improvement of the neutronic performance of the hybrid reactor rejuvenating spent fuels using various moderators. Fusion Technol. 34:1998;109.
    • (1998) Fusion Technol. , vol.34 , pp. 109
    • Ünalan, S.1    Akansu, S.O.2
  • 17
    • 0022101495 scopus 로고
    • Design of helium-cooled molten-salt fusion breeder
    • Moir R.W.et al. Design of helium-cooled molten-salt fusion breeder. Fusion Technol. 8:1985;465.
    • (1985) Fusion Technol. , vol.8 , pp. 465
    • Moir, R.W.1
  • 18
    • 0038269774 scopus 로고
    • Cost of processing fuel from a molten salt fusion/fission, hybrid reactor blanket
    • Watson J.S., Grimes W.R., Brashears D.E. Cost of processing fuel from a molten salt fusion/fission, hybrid reactor blanket. Fusion Technol. 12:1985;30.
    • (1985) Fusion Technol. , vol.12 , pp. 30
    • Watson, J.S.1    Grimes, W.R.2    Brashears, D.E.3
  • 19
    • 0023386614 scopus 로고
    • Updated reference design of a liquid-metal-cooled tandem mirror fusion breeder
    • Berwald D.H.et al. Updated reference design of a liquid-metal-cooled tandem mirror fusion breeder. Fusion Technol. 12:1987;30.
    • (1987) Fusion Technol. , vol.12 , pp. 30
    • Berwald, D.H.1
  • 20
    • 0028484578 scopus 로고
    • Basic requirements for a 1000 MW (electric) class Tokamak fusion-fission hybrid reactor and its blanket concept
    • Hatayama A.et al. Basic requirements for a 1000 MW (electric) class Tokamak fusion-fission hybrid reactor and its blanket concept. Fusion Technol. 26:1994;27.
    • (1994) Fusion Technol. , vol.26 , pp. 27
    • Hatayama, A.1
  • 21
    • 0023453520 scopus 로고
    • A hybrid blanket for a reversed-field pinch reactor
    • Jaeger J.F. A hybrid blanket for a reversed-field pinch reactor. Fusion Technol. 12:1991;364.
    • (1991) Fusion Technol. , vol.12 , pp. 364
    • Jaeger, J.F.1
  • 24
    • 0028336175 scopus 로고
    • HYLIFE-II: A molten salt inertial fusion energy power plant design - Final report
    • Moir R.W.et al. HYLIFE-II: a molten salt inertial fusion energy power plant design - final report. Fusion Technol. 25:1994;5.
    • (1994) Fusion Technol. , vol.25 , pp. 5
    • Moir, R.W.1
  • 32
    • 0003798821 scopus 로고
    • Tritium recovery from lithium, based on a cold trap
    • Sze D.-K.et al. Tritium recovery from lithium, based on a cold trap. Fusion Eng. Des. 28:1995;220.
    • (1995) Fusion Eng. Des. , vol.28 , pp. 220
    • Sze, D.-K.1
  • 33
    • 0032157243 scopus 로고    scopus 로고
    • Tritium processing system for the ITER Li/V blanket test module
    • Sze D.-K.et al. Tritium processing system for the ITER Li/V blanket test module. Fusion Eng. Des. 39-40:1998;859.
    • (1998) Fusion Eng. Des. , vol.39-40 , pp. 859
    • Sze, D.-K.1
  • 34
    • 0034315054 scopus 로고    scopus 로고
    • Tritium technology for blankets of fusion power plants
    • Fütterer M.A.et al. Tritium technology for blankets of fusion power plants. Fusion Eng. Des. 49-50:2000;735.
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 735
    • Fütterer, M.A.1
  • 36
    • 0019044810 scopus 로고
    • The effect of the spontaneous fission of plutonium-240 on energy release in a nuclear explosive
    • Şahin S., Ligou J. The effect of the spontaneous fission of plutonium-240 on energy release in a nuclear explosive. Nucl. Technol. 50:1980;88.
    • (1980) Nucl. Technol. , vol.50 , pp. 88
    • Şahin, S.1    Ligou, J.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.