메뉴 건너뛰기




Volumn 51, Issue 1, 2009, Pages 109-123

Fuel cycle analysis of GFR using advanced fuels

Author keywords

Advanced fuel cycle; GFR; Synergistic LWR fast reactor fuel cycles

Indexed keywords

ACTINIDES; AIR POLLUTION; FAST REACTORS; FUELS; FUSION REACTIONS; GAS COOLED REACTORS; INCINERATION; ISOTOPES; LIGHT WATER REACTORS; NEUTRON DETECTORS; NUCLEAR FUELS; NUCLEAR REACTORS; PLUTONIUM; REACTOR CORES; RECYCLING; ROUGHNESS MEASUREMENT; TRANSURANIUM ELEMENTS; URANIUM;

EID: 56949096283     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2007.12.005     Document Type: Article
Times cited : (10)

References (29)
  • 2
    • 0021477945 scopus 로고
    • Fission-product release during postirradiation annealing of several types of coated fuel particles
    • Bullock R.E. Fission-product release during postirradiation annealing of several types of coated fuel particles. Journal of Nuclear Materials 125 (1984) 304-319
    • (1984) Journal of Nuclear Materials , vol.125 , pp. 304-319
    • Bullock, R.E.1
  • 3
    • 2642518835 scopus 로고    scopus 로고
    • Chauvin, N., et al., 2003. Requirements for fuel and structural materials for Gas Cooled Fast Reactor (GFR), preliminary design. In: Proceedings of Global 2003, p. 2001.
    • Chauvin, N., et al., 2003. Requirements for fuel and structural materials for Gas Cooled Fast Reactor (GFR), preliminary design. In: Proceedings of Global 2003, p. 2001.
  • 5
    • 56949099195 scopus 로고    scopus 로고
    • Corwin, W., et al., Apr. 2004. The Gas Fast Reactor (GFR) Survey of Materials Experience and R&D Needs to Assess Viability. ORNL/TM-2004/99.
    • Corwin, W., et al., Apr. 2004. The Gas Fast Reactor (GFR) Survey of Materials Experience and R&D Needs to Assess Viability. ORNL/TM-2004/99.
  • 6
    • 56949104367 scopus 로고    scopus 로고
    • Croff, A.G., July 1980. A User's Manual For The ORIGEN2 Computer Code. ORNL/TM-7175.
    • Croff, A.G., July 1980. A User's Manual For The ORIGEN2 Computer Code. ORNL/TM-7175.
  • 8
    • 56949099342 scopus 로고    scopus 로고
    • Gauld, I.C., Bowman, S.M., Horwedel, J.E., 2006. ORIGEN-ARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay, and Source Term Analysis. ORNL/TM-2005/39 Revision 5.1, Vol. I, Book 2, Sect. D1, SCALE 5 Manual, April.
    • Gauld, I.C., Bowman, S.M., Horwedel, J.E., 2006. ORIGEN-ARP: Automatic Rapid Processing for Spent Fuel Depletion, Decay, and Source Term Analysis. ORNL/TM-2005/39 Revision 5.1, Vol. I, Book 2, Sect. D1, SCALE 5 Manual, April.
  • 10
    • 33845727123 scopus 로고    scopus 로고
    • Greneche, D., Vinoche, R., Delpeh, M., Golfier, H., 2006. Neptunium as a tool for reducing proliferation risks with plutonium: a technical analysis of its efficiency and its drawbacks. In: Proceedings of International Congress on Advances in Nuclear Power Plants, ICAPP '06, paper 6133.
    • Greneche, D., Vinoche, R., Delpeh, M., Golfier, H., 2006. Neptunium as a tool for reducing proliferation risks with plutonium: a technical analysis of its efficiency and its drawbacks. In: Proceedings of International Congress on Advances in Nuclear Power Plants, ICAPP '06, paper 6133.
  • 11
    • 0038347111 scopus 로고    scopus 로고
    • Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets
    • Grouiller J. Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets. Journal of Nuclear Materials 320 (2003) 163-169
    • (2003) Journal of Nuclear Materials , vol.320 , pp. 163-169
    • Grouiller, J.1
  • 12
    • 0036388177 scopus 로고    scopus 로고
    • Hill, R.N., et al., 2002. Multiple tier fuel cycle studies for waste transmutation. In: Proceedings of ICONE 10, 10th International Conference on Nuclear Engineering, April 14-18, 2002, Arlington, VA.
    • Hill, R.N., et al., 2002. Multiple tier fuel cycle studies for waste transmutation. In: Proceedings of ICONE 10, 10th International Conference on Nuclear Engineering, April 14-18, 2002, Arlington, VA.
  • 14
    • 85044699256 scopus 로고    scopus 로고
    • ICRP Publication 72: Age-dependent doses to the members of the public from intake of radionuclides part 5, compilation of ingestion and inhalation coefficients
    • International Commission on Radiological Protection (ICRP). ICRP Publication 72: Age-dependent doses to the members of the public from intake of radionuclides part 5, compilation of ingestion and inhalation coefficients. Annals of the ICRP 26 1 (Sep. 1996)
    • (1996) Annals of the ICRP , vol.26 , Issue.1
    • International Commission on Radiological Protection (ICRP)1
  • 15
    • 0033705246 scopus 로고    scopus 로고
    • 244Cm by track-etch-cum-gamma spectrometry
    • 244Cm by track-etch-cum-gamma spectrometry. Nuclear Science and Engineering 135 (2000) 227-245
    • (2000) Nuclear Science and Engineering , vol.135 , pp. 227-245
    • Iyer, R.H.1
  • 17
    • 56949084350 scopus 로고    scopus 로고
    • Meyer, M.K., 2003. Overview of gas fast reactor inert matrix fuel candidates. In: Proceedings of Global 2003, November 16-18.
    • Meyer, M.K., 2003. Overview of gas fast reactor inert matrix fuel candidates. In: Proceedings of Global 2003, November 16-18.
  • 18
    • 56949099194 scopus 로고    scopus 로고
    • MCNP - A General Monte Carlo N-Particle Transport Code, 2005. Version 5, Revised 10/3/05, LA-UR-03-1987, Los Alamos National Laboratory X-5 Monte Carlo Team.
    • MCNP - A General Monte Carlo N-Particle Transport Code, 2005. Version 5, Revised 10/3/05, LA-UR-03-1987, Los Alamos National Laboratory X-5 Monte Carlo Team.
  • 24
    • 56949084090 scopus 로고    scopus 로고
    • Poston, D.I., Trellue, H.R., 1999. RSICC MONTEBURNS 2.0 PSR-455, An Automated, Multi-Step Monte Carlo Burnup Code System. LA-UR-99-4999 User's Manual, Version 2.0, for Monteburns, Version 1.0.
    • Poston, D.I., Trellue, H.R., 1999. RSICC MONTEBURNS 2.0 PSR-455, An Automated, Multi-Step Monte Carlo Burnup Code System. LA-UR-99-4999 User's Manual, Version 2.0, for Monteburns, Version 1.0.
  • 25
    • 0029403477 scopus 로고
    • Correlations of the independent fission product yields of different isotopes
    • Ronen Y. Correlations of the independent fission product yields of different isotopes. Nuclear Science and Engineering 121 (1995) 483-491
    • (1995) Nuclear Science and Engineering , vol.121 , pp. 483-491
    • Ronen, Y.1
  • 26
    • 22944462367 scopus 로고    scopus 로고
    • Optimum discharge burnup and cycle length for PWRs
    • Secker J.R., et al. Optimum discharge burnup and cycle length for PWRs. Nuclear Technology 151 (2005) 109
    • (2005) Nuclear Technology , vol.151 , pp. 109
    • Secker, J.R.1
  • 27
    • 56949084778 scopus 로고    scopus 로고
    • U.S. Department of Energy Office of Civilian Radioactive Waste Management (DOE), Feb. 2002. Yucca Mountain Science and Engineering Report Technical Information Supporting Site Recommendation Consideration Revision 1.
    • U.S. Department of Energy Office of Civilian Radioactive Waste Management (DOE), Feb. 2002. Yucca Mountain Science and Engineering Report Technical Information Supporting Site Recommendation Consideration Revision 1.
  • 28
    • 56949086324 scopus 로고    scopus 로고
    • Vandegrift, G.F., 2004. Lab-scale demonstration of the UREX + process. WM'04 Conference, Tucson, AZ, February 29-March 4.
    • Vandegrift, G.F., 2004. Lab-scale demonstration of the UREX + process. WM'04 Conference, Tucson, AZ, February 29-March 4.
  • 29
    • 34249047321 scopus 로고    scopus 로고
    • Wei, T.Y.C., Hejzlar, P., Feldman, E.E., Williams, W.C., 2005. A semi-passive approach to GFR depressurized decay heat removal accidents. In: Proceedings of International Congress on Advances in Nuclear Power Plants, ICAPP '05, paper 5007.
    • Wei, T.Y.C., Hejzlar, P., Feldman, E.E., Williams, W.C., 2005. A semi-passive approach to GFR depressurized decay heat removal accidents. In: Proceedings of International Congress on Advances in Nuclear Power Plants, ICAPP '05, paper 5007.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.