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Volumn 31, Issue 1-2, 1997, Pages 83-110

Metallic fast reactor fuels

Author keywords

EBR II; Electrorefining; Fast reactor; IFR; Liquid metal reactor; LMR; Metallic fuel; Nuclear fuel cycle; Plutonium; Reactor design; Reactor safety; Recycling

Indexed keywords


EID: 0001843947     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/0149-1970(96)00005-4     Document Type: Article
Times cited : (383)

References (57)
  • 2
    • 0011808243 scopus 로고
    • A theory of swelling and gas release for reactor materials
    • Barnes, R.S. (1964). A Theory of Swelling and Gas Release for Reactor Materials. Journal of Nuclear Materials 11, 135.
    • (1964) Journal of Nuclear Materials , vol.11 , pp. 135
    • Barnes, R.S.1
  • 3
    • 0043258377 scopus 로고
    • Run-Beyond-Cladding Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program
    • Snowbird, Utah, 12-16 August
    • Batté, G. and G.L. Hofman (1990). Run-Beyond-Cladding Breach (RBCB) Test Results for the Integral Fast Reactor (IFR) Metallic Fuels Program. International Fast Reactor Safety Meeting IV, p.207, Snowbird, Utah, 12-16 August.
    • (1990) International Fast Reactor Safety Meeting IV , pp. 207
    • Batté, G.1    Hofman, G.L.2
  • 4
    • 0041755326 scopus 로고
    • Integral fast reactor metallic fuel program in pile measurement of the thermal conductivity of irradiated metallic fuel
    • Bauer, T.H. and J.W. Holland (1992). Integral Fast Reactor Metallic Fuel Program in Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel. Transactions of the American Nuclear Society 65, 278.
    • (1992) Transactions of the American Nuclear Society , vol.65 , pp. 278
    • Bauer, T.H.1    Holland, J.W.2
  • 6
    • 0029322783 scopus 로고
    • In-pile measurement of the thermal conductivity of irradiated metallic fuel
    • Bauer, T.H. and J.W. Holland (1995). In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel. Nuclear Technology 110, 407.
    • (1995) Nuclear Technology , vol.110 , pp. 407
    • Bauer, T.H.1    Holland, J.W.2
  • 8
    • 0042757222 scopus 로고
    • Fission gas release and thermal conductivity measurements on U-5 Wt % Fs irradiated in CP-5
    • Beck, W.N. and R.J. Fousek (1969). Fission Gas Release and Thermal Conductivity Measurements on U-5 Wt % Fs Irradiated in CP-5. Transactions of the American Nuclear Society 12, 78.
    • (1969) Transactions of the American Nuclear Society , vol.12 , pp. 78
    • Beck, W.N.1    Fousek, R.J.2
  • 10
    • 0040718785 scopus 로고
    • In-core measurements of uranium - 5 wt.% fissium alloy thermal conductivity
    • Betten, P.R. (1985). In-Core Measurements of Uranium - 5 wt.% Fissium Alloy Thermal Conductivity. Transactions of the American Nuclear Society 50, 239.
    • (1985) Transactions of the American Nuclear Society , vol.50 , pp. 239
    • Betten, P.R.1
  • 11
    • 0042757223 scopus 로고
    • Achieving high burn-up in fast reactors
    • Blake, L.R. (1961). Achieving High Burn-up in Fast Reactors. Reactor Science and Technology 14, 31.
    • (1961) Reactor Science and Technology , vol.14 , pp. 31
    • Blake, L.R.1
  • 12
    • 0039533396 scopus 로고
    • Thermomigration and electromigration in zirconium
    • Campbell, D.R. and H.B Huntington (1969). Thermomigration and Electromigration in Zirconium. Physical Review 179, 601.
    • (1969) Physical Review , vol.179 , pp. 601
    • Campbell, D.R.1    Huntington, H.B.2
  • 13
    • 0024755944 scopus 로고
    • The integral fast reactor
    • Chang, Y.I. (1989). The Integral Fast Reactor. Nuclear Technology 88, 129.
    • (1989) Nuclear Technology , vol.88 , pp. 129
    • Chang, Y.I.1
  • 17
    • 0019923316 scopus 로고
    • Fast-neutron hodoscope at treat: Methods for quantitative determination of fuel dispersal
    • DeVolpi, A., C.L. Fink, G.E. Marsh, E.A Rhodes, and G.S. Stanford (1982). Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal, Nuclear Technology 56, 141.
    • (1982) Nuclear Technology , vol.56 , pp. 141
    • DeVolpi, A.1    Fink, C.L.2    Marsh, G.E.3    Rhodes, E.A.4    Stanford, G.S.5
  • 20
    • 0041755318 scopus 로고
    • The effects of neutron irradiation on λ-uranium and some fissile alloys of cubic crystal structure
    • Greenwood, G.W. (1962). The Effects of Neutron Irradiation on λ-Uranium and Some Fissile Alloys of Cubic Crystal Structure. Journal of Nuclear Materials 6-1, 26.
    • (1962) Journal of Nuclear Materials , vol.6 , Issue.1 , pp. 26
    • Greenwood, G.W.1
  • 22
    • 0018943825 scopus 로고
    • Irradiation behavior of experimental mark-II EBR-II driver fuel
    • Hofman, G.L. (1980). Irradiation Behavior of Experimental Mark-II EBR-II Driver Fuel. Nuclear Technology 47, 7.
    • (1980) Nuclear Technology , vol.47 , pp. 7
    • Hofman, G.L.1
  • 27
    • 0025387148 scopus 로고
    • Development of the SESAMI metallic fuel performance code
    • Kobayashi, T., M. Kinoshita and S. Hattori (1990). Development of the SESAMI Metallic Fuel Performance Code. Nuclear Technology 89, 183.
    • (1990) Nuclear Technology , vol.89 , pp. 183
    • Kobayashi, T.1    Kinoshita, M.2    Hattori, S.3
  • 32
    • 0042757175 scopus 로고
    • Etude du gonflenent d'alliages d'uranium sous irradiation
    • Lehmann, J.P. Paoli, N. Azam (1968). Etude du Gonflenent d'Alliages d'Uranium Sous Irradiation. Journal of Nuclear Materials 27, 285.
    • (1968) Journal of Nuclear Materials , vol.27 , pp. 285
    • Lehmann1    Paoli, J.P.2    Azam, N.3
  • 38
    • 0014891968 scopus 로고
    • The uranium-plutonium-zirconium ternary alloy system
    • American Institute of Metallurgical Engineering
    • O'Boyle D.R. and A.E. Dwight (1970). The Uranium-Plutonium-Zirconium Ternary Alloy System. Plutonium 1970 and Other Actinides Nuclear Metallurgy, 17, American Institute of Metallurgical Engineering.
    • (1970) Plutonium 1970 and Other Actinides Nuclear Metallurgy , vol.17
    • O'Boyle, D.R.1    Dwight, A.E.2
  • 41
    • 0025459086 scopus 로고
    • Fuel constituent redistribution during the early stages of U-Pu-Zr irradiation
    • Porter, D.L., C.E. Lahm and R.G. Pahl (1990). Fuel Constituent Redistribution During the Early Stages of U-Pu-Zr Irradiation. Metallurgical Transactions A, 21A, 1871.
    • (1990) Metallurgical Transactions A , vol.21 A , pp. 1871
    • Porter, D.L.1    Lahm, C.E.2    Pahl, R.G.3
  • 42
    • 0041755290 scopus 로고
    • Swelling in alpha uranium due to irradiation
    • University of Chicago Press, Chap. XXXI
    • Pugh, S.F. (1961). Swelling in Alpha Uranium Due to Irradiation. The Metal Plutonium, University of Chicago Press, Chap. XXXI.
    • (1961) The Metal Plutonium
    • Pugh, S.F.1
  • 45
    • 0043258338 scopus 로고
    • Radiation Effects in Breeder Reactor Structural Materials, American Institute of Metallurgical Engineering, Chicago, Illinois
    • Seidel, B.R. and R.E. Einziger (1977). In-Reactor Cladding Breach of EBR-II Driver Fuel Elements, Radiation Effects in Breeder Reactor Structural Materials, American Institute of Metallurgical Engineering, Chicago, Illinois.
    • (1977) In-reactor Cladding Breach of EBR-II Driver Fuel Elements
    • Seidel, B.R.1    Einziger, R.E.2
  • 51
    • 30844433420 scopus 로고
    • Fuel/cladding compatibility in irradiated metallic fuel pins at elevated temperatures
    • Snowbird, Utah, 12-16 August
    • Tsai, H. (1990). Fuel/Cladding Compatibility in Irradiated Metallic Fuel Pins at Elevated Temperatures. International Fast Reactor Safety Meeting II, p.257, Snowbird, Utah, 12-16 August.
    • (1990) International Fast Reactor Safety Meeting II , pp. 257
    • Tsai, H.1
  • 52
    • 84874413249 scopus 로고
    • Behavior of low-burnup metallic fuels for the integral fast reactor at elevated temperatures in ex-reactor tests
    • Kyoto, Japan, 13 October
    • Tsai, H. (1991). Behavior of Low-Burnup Metallic Fuels for the Integral Fast Reactor at Elevated Temperatures in Ex-Reactor Tests. Conference on Fast Reactors and Related Fuel Cycles III, 1.18-1, Kyoto, Japan, 13 October.
    • (1991) Conference on Fast Reactors and Related Fuel Cycles III , vol.1 , pp. 18-21
    • Tsai, H.1
  • 54
  • 56
    • 0021425275 scopus 로고
    • Performance of metallic fuels and blankets in liquid-metal fast breeder reactors
    • Walters, L.C., B.R. Seidel and J.H. Kittel (1984). Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors. Nuclear Technology 65, 179.
    • (1984) Nuclear Technology , vol.65 , pp. 179
    • Walters, L.C.1    Seidel, B.R.2    Kittel, J.H.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.