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Volumn 44, Issue 3, 2003, Pages 439-458

Analysis of the neutronic data in infinite medium using fusion neutron source for various material compositions

Author keywords

Fissile fuel breeding; Fusion neutron; Heat release; Infinite medium; Net neutron gain

Indexed keywords

FISSION REACTIONS; FUSION REACTIONS; FUSION REACTORS; VOLUME FRACTION;

EID: 0037289975     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0196-8904(02)00059-6     Document Type: Article
Times cited : (2)

References (30)
  • 1
    • 0343391108 scopus 로고    scopus 로고
    • Basic study on characteristics of some important equilibrium fuel cycles of PWR
    • Technical Note
    • Waris A., Sekimoto H. Basic study on characteristics of some important equilibrium fuel cycles of PWR. Technical Note, Ann Nucl Energy. 28:2001;153-167.
    • (2001) Ann Nucl Energy , vol.28 , pp. 153-167
    • Waris, A.1    Sekimoto, H.2
  • 2
    • 0035254619 scopus 로고    scopus 로고
    • Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel
    • Şahin S., Özceyhan V., Yapici H. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel. Ann Nucl Energy. 28:2001;204-223.
    • (2001) Ann Nucl Energy , vol.28 , pp. 204-223
    • Şahin, S.1    Özceyhan, V.2    Yapici, H.3
  • 3
    • 0004055594 scopus 로고    scopus 로고
    • International Atomic Energy Agency, Vienna
    • IAEA. Sustainable Development and Nuclear Power. International Atomic Energy Agency, Vienna, 1997. p. 8-10.
    • (1997) Sustainable Development and Nuclear Power , pp. 8-10
  • 4
    • 17044460297 scopus 로고
    • Global energy scenarios and the potential role of fusion energy in the 21st century
    • Pease R.S. Global energy scenarios and the potential role of fusion energy in the 21st century. J Nucl Mater. 191-194:1992;7-14.
    • (1992) J Nucl Mater , vol.191-194 , pp. 7-14
    • Pease, R.S.1
  • 5
    • 0026897752 scopus 로고
    • Fusion power from lunar resources
    • Kulcinki G. et al. Fusion power from lunar resources. Fusion Technol. 21:1992;2221-2229.
    • (1992) Fusion Technol , vol.21 , pp. 2221-2229
    • Kulcinki, G.1
  • 6
    • 0001242820 scopus 로고
    • Waste disposal assessment of HYLIEE-II structure
    • Lee J.D. Waste disposal assessment of HYLIEE-II structure. Fusion Technol. 26(4):1994;174.
    • (1994) Fusion Technol , vol.26 , Issue.4 , pp. 174
    • Lee, J.D.1
  • 9
    • 0028484578 scopus 로고
    • Basic requirements for a 1000-MW (electric) class tokamak fusion-fission hybrid reactor and its blanket concept
    • Hatayama A., Ogasawara M. et al. Basic requirements for a 1000-MW (electric) class tokamak fusion-fission hybrid reactor and its blanket concept. Fusion Technol. 26:1994;27-45.
    • (1994) Fusion Technol , vol.26 , pp. 27-45
    • Hatayama, A.1    Ogasawara, M.2
  • 10
    • 0032340192 scopus 로고    scopus 로고
    • Evaluation of the integral quantities for incident fusion source neutrons in infinite medium
    • Şahin S., Yapici H., Özceyhan V. Evaluation of the integral quantities for incident fusion source neutrons in infinite medium. Ann Nucl Energy. 25(18):1998;1503.
    • (1998) Ann Nucl Energy , vol.25 , Issue.18 , pp. 1503
    • Şahin, S.1    Yapci, H.2    Özceyhan, V.3
  • 14
    • 0033692734 scopus 로고    scopus 로고
    • Neutronic analysis of flux dispersion in a multi-layered, (D-T) driven hybrid blanket
    • TUBITAK
    • Ipek O. Neutronic analysis of flux dispersion in a multi-layered, (D-T) driven hybrid blanket. Turkish J Engng Environ Sci, TUBITAK. 24:2000;373-382.
    • (2000) Turkish J Engng Environ Sci , vol.24 , pp. 373-382
    • Ipek, O.1
  • 15
    • 0019623224 scopus 로고
    • Recent progress in fusion-fission (hybrid) reactor design studies
    • Maniscalo J.A. et al. Recent progress in fusion-fission (hybrid) reactor design studies. Nucl Technol/Fusion. 1(4):1981;419.
    • (1981) Nucl Technol/Fusion , vol.1 , Issue.4 , pp. 419
    • Maniscalo, J.A.1
  • 16
    • 0003167471 scopus 로고    scopus 로고
    • Decrease of the LWR spent nuclear waste inventories and cumulative fissile fuel enrichment in hybrid reactor system, ICONE-8348
    • April 2-6, Baltimore, MD USA Copyright © 2000 ASME
    • Ipek O. Decrease of the LWR spent nuclear waste inventories and cumulative fissile fuel enrichment in hybrid reactor system, ICONE-8348. In: Proceeding of ICONE 8, 8th International Conference on Nuclear Engineering, April 2-6, Baltimore, MD USA Copyright © 2000 ASME, 2000.
    • (2000) Proceeding of ICONE 8, 8th International Conference on Nuclear Engineering
    • Ipek, O.1
  • 17
    • 0035546628 scopus 로고    scopus 로고
    • Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D-T) driven hybrid reactor system
    • Pergamon
    • Yapici H., Ipek O., Özceyhan V. Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D-T) driven hybrid reactor system. Pergamon, Ann Nucl Energy. 2B:2001;1825-1850.
    • (2001) Ann Nucl Energy , vol.2 B , pp. 1825-1850
    • Yapici, H.1    Ipek, O.2    Özceyhan, V.3
  • 18
    • 0002338364 scopus 로고    scopus 로고
    • Decrease of the CANDU spent nuclear waste inventories in fusion-fission (hybrid) reactors
    • Şahin S., Unalan U., Yapici H. Decrease of the CANDU spent nuclear waste inventories in fusion-fission (hybrid) reactors. Int J Energy Environ Econom. 4(1):1996;67-97.
    • (1996) Int J Energy Environ Econom , vol.4 , Issue.1 , pp. 67-97
    • Şahin, S.1    Unalan, U.2    Yapici, H.3
  • 19
    • 0022752722 scopus 로고
    • Preliminarily design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driven
    • Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminarily design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driven. Fusion Technol. 10:1986;84.
    • (1986) Fusion Technol , vol.10 , pp. 84
    • Şahin, S.1    Al-Kusayer, T.A.2    Raoof, M.A.3
  • 20
    • 0010728883 scopus 로고    scopus 로고
    • Potential of a fusion-fission hybrid reactor using for various coolants to breed fissile fuel for LWRs
    • Elsevier Pergamon, Received 23 July, accepted 27 October, UK
    • Yaipci H., Cürtüttü I., Özceyhan V., et al. Potential of a fusion-fission hybrid reactor using for various coolants to breed fissile fuel for LWRs. Ann Nucl Energy, Elsevier Pergamon, Received 23 July, accepted 27 October, UK, 1998.
    • (1998) Ann Nucl Energy
    • Yaipci, H.1    Cürtüttü, I.2    Özceyhan, V.3
  • 21
    • 0021389767 scopus 로고
    • Blanket design and calculated performance for the LOTUS fusion-fission hybrid test facility
    • Abdul K.S., Haldy P.A., Kumar A. Blanket design and calculated performance for the LOTUS fusion-fission hybrid test facility. Nucl Tech/Fusion. 5:1984;189.
    • (1984) Nucl Tech/Fusion , vol.5 , pp. 189
    • Abdul, K.S.1    Haldy, P.A.2    Kumar, A.3
  • 25
    • 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
  • 26
    • 0033241679 scopus 로고    scopus 로고
    • Pertinent integral data per fusion neutron in infinite medium
    • Şahin S., Yapici H., Özceyhan V. Pertinent integral data per fusion neutron in infinite medium. Arab J Sci Engng. 24(2A):1999;149-163.
    • (1999) Arab J Sci Engng , vol.24 , Issue.2 A , pp. 149-163
    • Şahin, S.1    Yapici, H.2    Özceyhan, V.3
  • 27
    • 0001664844 scopus 로고    scopus 로고
    • The infinite medium Green's function in space and angle for the integro-differential form of the neutron transport equation with isotopic scattering
    • Cassell J.S., Williams M.M.R. The infinite medium Green's function in space and angle for the integro-differential form of the neutron transport equation with isotopic scattering. Ann Nucl Energy. 27:2001;11-19.
    • (2001) Ann Nucl Energy , vol.27 , pp. 11-19
    • Cassell, J.S.1    Williams, M.M.R.2
  • 28
    • 0035400952 scopus 로고    scopus 로고
    • The infinite medium Green's function method for multi-group discrete ordinates transport problems in multi-layered slab geometry
    • Hong S.G., Cho N.Z. The infinite medium Green's function method for multi-group discrete ordinates transport problems in multi-layered slab geometry. Ann Nucl Energy. 28:2001;1102-1114.
    • (2001) Ann Nucl Energy , vol.28 , pp. 1102-1114
    • Hong, S.G.1    Cho, N.Z.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.