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Volumn , Issue , 2007, Pages 671-678

Minor actinide transmutation for low conversion ratio sodium fast reactors

Author keywords

[No Author keywords available]

Indexed keywords

(LIQUID + LIQUID) EQUILIBRIUM; CLOSED CYCLE; CLOSED FUEL CYCLES; CONVERSION RATIOS; DECAY HEATING; GAMMA ENERGY; INERT MATRIX FUEL (IMF); LIGHT WATER; LOW-CONVERSION RATIO; METAL FUELS; MINOR ACTINIDE (MA); MINOR ACTINIDE TRANSMUTATION; MINOR ACTINIDES (MA); MIXED OXIDE (MOX); NUCLEAR-FUEL CYCLES; PYROPROCESSING; SPENT NUCLEAR FUEL (SNF); TRANSURANIC (TRU) ELEMENTS;

EID: 45149132204     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (2)

References (14)
  • 1
    • 0002115141 scopus 로고    scopus 로고
    • The Design Rationale of the IFR
    • D. C. WADE, R. N. HILL, "The Design Rationale of the IFR," Progress in Nuclear Energy, 31, 1-2, 13-42 (1997).
    • (1997) Progress in Nuclear Energy , vol.31 , Issue.1-2 , pp. 13-42
    • WADE, D.C.1    HILL, R.N.2
  • 5
    • 0029378548 scopus 로고
    • Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle
    • R. N. HILL, D. C. WADE, J. R. LIAW, and E. K. FUJITA, "Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle," Nuclear Science and Engineering, 121, 17 (1995).
    • (1995) Nuclear Science and Engineering , vol.121 , pp. 17
    • HILL, R.N.1    WADE, D.C.2    LIAW, J.R.3    FUJITA, E.K.4
  • 6
    • 45149116166 scopus 로고    scopus 로고
    • Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios
    • E. A. HOFFMAN, W. S. YANG, and R. N. HILL, "Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios," Argonne National Laboratory, ANL-AFCI-177 (2006).
    • (2006) Argonne National Laboratory, ANL-AFCI-177
    • HOFFMAN, E.A.1    YANG, W.S.2    HILL, R.N.3
  • 7
    • 2642548275 scopus 로고    scopus 로고
    • Physics and Safety Studies of Low Conversion Ratio Sodium Cooled Fast Reactors
    • New Orleans, Louisiana, United States, pp, November 16-20
    • M. A. SMITH, E. E. MORRIS, R. N. HILL, "Physics and Safety Studies of Low Conversion Ratio Sodium Cooled Fast Reactors", Global 2003, New Orleans, Louisiana, United States, pp. 423-433, November 16-20 (2003).
    • (2003) Global 2003 , pp. 423-433
    • SMITH, M.A.1    MORRIS, E.E.2    HILL, R.N.3
  • 8
    • 0842312835 scopus 로고
    • 2-2: A Code to Calculate Fast Neutron Spectra and Multi-Group Cross-Sections
    • Argonne National Laboratory
    • 2-2: A Code to Calculate Fast Neutron Spectra and Multi-Group Cross-Sections." ANL-8144, Argonne National Laboratory (1976).
    • (1976) ANL-8144
    • HENRYSON II, H.1    TOPPEL, B.J.2    STENBERG, C.G.3
  • 9
    • 1842603493 scopus 로고
    • A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability
    • Argonne National Laboratory
    • B. J. Toppel, "A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability," ANL-83-2, Argonne National Laboratory (1983).
    • (1983) ANL-83-2
    • Toppel, B.J.1
  • 11
    • 0027658819 scopus 로고
    • Status of Fuel, Blanket, and Absorber Testing in the Fast Flux Test Facility
    • R. B. BAKER, F. E. BARD, R. D. LEGGETT, and A. L. PINTER, "Status of Fuel, Blanket, and Absorber Testing in the Fast Flux Test Facility," Journal of Nuclear Materials, 204, 109 ( 1993).
    • (1993) Journal of Nuclear Materials , vol.204 , pp. 109
    • BAKER, R.B.1    BARD, F.E.2    LEGGETT, R.D.3    PINTER, A.L.4
  • 13
    • 45149084788 scopus 로고    scopus 로고
    • SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732
    • SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.
  • 14
    • 45149090247 scopus 로고    scopus 로고
    • ORIGEN-S: Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, Version 5.1, II, Book 1, Sect. F7, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732
    • ORIGEN-S: Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, Version 5.1, Vol. II, Book 1, Sect. F7, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.