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Volumn 40, Issue 7, 2008, Pages 581-592

A conceptual study of pyroprocessing for recovering actinides from spent oxide fuels

Author keywords

Non proliferation; Nuclear fuel cycle; Pyroprocessing; Separation of actinides

Indexed keywords


EID: 58149231160     PISSN: 17385733     EISSN: None     Source Type: Journal    
DOI: 10.5516/NET.2008.40.7.581     Document Type: Article
Times cited : (93)

References (18)
  • 1
    • 85036864093 scopus 로고    scopus 로고
    • Hee-Seong Shin, Nuclear data obtained from the ORIGEN2, v2.1, Spontaneous fission neutron source from irradiation of PWR fuel, Korea Atomic Energy Research Institute, 2007.
    • Hee-Seong Shin, Nuclear data obtained from the ORIGEN2, v2.1, "Spontaneous fission neutron source from irradiation of PWR fuel", Korea Atomic Energy Research Institute, 2007.
  • 4
    • 85036857711 scopus 로고    scopus 로고
    • M.Salvatores et al, Assessment of pyrochemical processes for separation/transmutation strategies, DRRV/Dir/00-92, CEA, France (2000).
    • M.Salvatores et al, "Assessment of pyrochemical processes for separation/transmutation strategies", PG-DRRV/Dir/00-92, CEA, France (2000).
  • 6
    • 58149253119 scopus 로고    scopus 로고
    • Prediction of a mutual separation of actinide and rare earth groups in a multistage reductive extraction system
    • Jae-Hyung Yoo, Han-Soo Lee and Eung-Ho Kim, "Prediction of a mutual separation of actinide and rare earth groups in a multistage reductive extraction system", Nucl. Eng. & Tech. 39, 5 (2007).
    • (2007) Nucl. Eng. & Tech , vol.39 , pp. 5
    • Yoo, J.-H.1    Lee, H.-S.2    Kim, E.-H.3
  • 9
    • 85036870435 scopus 로고    scopus 로고
    • Jae-Hyung Yoo et al, Design study of advanced nuclear fuel cycle system(II)-Establishment of the concept of the recycle system using molten salt, KAERI/TS-196, 2004 (Translation report of JNC TN 9400 98-003).
    • Jae-Hyung Yoo et al, "Design study of advanced nuclear fuel cycle system(II)-Establishment of the concept of the recycle system using molten salt", KAERI/TS-196, 2004 (Translation report of JNC TN 9400 98-003).
  • 10
    • 0004730573 scopus 로고    scopus 로고
    • committee on electrometallurgical techniques for DOE spent fuel treatment, USA, National Academy Press, Washington, D.C
    • G.R. Choppin et al, committee on electrometallurgical techniques for DOE spent fuel treatment, USA, "Electrometallurgicat Techniques for DOE Spent Fuel Treatment", National Academy Press, Washington, D.C. (2000).
    • (2000) Electrometallurgicat Techniques for DOE Spent Fuel Treatment
    • Choppin, G.R.1
  • 11
    • 85036892114 scopus 로고    scopus 로고
    • Laurie M. Unger, D.K. Trubey, Specific Gamma-ray Dose Constants for Nuclides Important to Dosimetry and Radiological Assessment, ORNL/ RSIC-45/RI, Oak Ridge National Laboratory (1982).
    • Laurie M. Unger, D.K. Trubey, "Specific Gamma-ray Dose Constants for Nuclides Important to Dosimetry and Radiological Assessment", ORNL/ RSIC-45/RI, Oak Ridge National Laboratory (1982).
  • 12
    • 0043258441 scopus 로고
    • Self-Protection in Dry Recycle Technologies
    • Argonne National Laboratory
    • W.H.Hannum, D.Wade and G. Stanford, "Self-Protection in Dry Recycle Technologies", Argonne National Laboratory, Proc. Global '95, p.83 (1995).
    • (1995) Proc. Global '95 , pp. 83
    • Hannum, W.H.1    Wade, D.2    Stanford, G.3
  • 13
    • 58149256205 scopus 로고    scopus 로고
    • A Safer Nuclear Fuel Management Strategy without Sensitive Technology land Weapon Useable Material
    • Tsukuba, Japan, Oct 9-13
    • L.Koch, T.Inoue, T.Yokoo, "A Safer Nuclear Fuel Management Strategy without Sensitive Technology land Weapon Useable Material", Proc. Global 2005, Tsukuba, Japan, Oct 9-13, 2005.
    • (2005) Proc. Global 2005
    • Koch, L.1    Inoue, T.2    Yokoo, T.3
  • 15
    • 85036873636 scopus 로고    scopus 로고
    • J.A.Stone, D.R.Johnson, Measurement of Radioactive Gaseous Effluents from Voloxidation and Dissolution of Spent Nuclear Fuel, DP-MS-78-7, Savannah River Lab. (1978).
    • J.A.Stone, D.R.Johnson, "Measurement of Radioactive Gaseous Effluents from Voloxidation and Dissolution of Spent Nuclear Fuel", DP-MS-78-7, Savannah River Lab. (1978).
  • 17
    • 0033077657 scopus 로고    scopus 로고
    • Separation of Uranium and Transuranic Elements from Tare earth Elements by Means of Multistage Extraction in LiCl-KCI/Bi System
    • K.Kinoshita et al, "Separation of Uranium and Transuranic Elements from Tare earth Elements by Means of Multistage Extraction in LiCl-KCI/Bi System", J. Nucl. Sci. and Tech. 36, 2 p.189-197 (1999).
    • (1999) J. Nucl. Sci. and Tech , vol.36 , Issue.2 , pp. 189-197
    • Kinoshita, K.1
  • 18
    • 34247106202 scopus 로고    scopus 로고
    • Electrolytic Reduction of Spent Light Water Reactor Fuel
    • S.Herrmann, S.Li and M. Simpson, "Electrolytic Reduction of Spent Light Water Reactor Fuel", J. Nucl. Sci. and Tech. 44, 3 p.361-367 (2007).
    • (2007) J. Nucl. Sci. and Tech , vol.44 , Issue.3 , pp. 361-367
    • Herrmann, S.1    Li, S.2    Simpson, M.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.