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Volumn 444-445, Issue SPEC. ISS., 2007, Pages 434-437

Weapons-Grade MOX fuel burnup characteristics in Advanced Test Reactor irradiation

Author keywords

MCNP; MCWO; ORIGEN 2; Weapons Grade Mixed Oxide fuel

Indexed keywords

CHEMICAL WARFARE; CODES (STANDARDS); COMBUSTION; ELECTRON IRRADIATION; NUCLEAR REACTOR ACCIDENTS;

EID: 34548140171     PISSN: 09258388     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jallcom.2007.02.158     Document Type: Article
Times cited : (6)

References (12)
  • 2
    • 0001378131 scopus 로고
    • ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
    • Croff A.G. ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials. Nucl. Technol. 62 (1983) 335-352
    • (1983) Nucl. Technol. , vol.62 , pp. 335-352
    • Croff, A.G.1
  • 3
    • 0033903107 scopus 로고    scopus 로고
    • Depletion analysis of mixed oxide fuel pins in light water reactors and the advanced test reactor
    • Chang G.S., and Ryskamp J.M. Depletion analysis of mixed oxide fuel pins in light water reactors and the advanced test reactor. Nucl. Technol. 129 3 (2000) 326-337
    • (2000) Nucl. Technol. , vol.129 , Issue.3 , pp. 326-337
    • Chang, G.S.1    Ryskamp, J.M.2
  • 4
    • 33644610373 scopus 로고    scopus 로고
    • MCWO-linking MCNP and ORIGEN2 for fuel burnup analysis
    • Chattanooga, Tennessee, April 17-21, 2005 on CD-ROM, American Nuclear Society, LaGrange Park, IL
    • Chang G.S. MCWO-linking MCNP and ORIGEN2 for fuel burnup analysis. Proceedings of the Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World. Chattanooga, Tennessee, April 17-21, 2005 on CD-ROM (2005), American Nuclear Society, LaGrange Park, IL
    • (2005) Proceedings of the Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World
    • Chang, G.S.1
  • 5
    • 0343454138 scopus 로고    scopus 로고
    • Neutron flux and spectrum variation in a MOX fuel experiment
    • Chang G.S., Rogers J.W., and Ryskamp J.M. Neutron flux and spectrum variation in a MOX fuel experiment. Trans. Am. Nucl. Soc. 81 (1999) 284
    • (1999) Trans. Am. Nucl. Soc. , vol.81 , pp. 284
    • Chang, G.S.1    Rogers, J.W.2    Ryskamp, J.M.3
  • 6
    • 34548142803 scopus 로고    scopus 로고
    • Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method), ASTM Standards, E-321-96.
  • 7
    • 34548129428 scopus 로고    scopus 로고
    • R.N. Morris, C.A. Baldwin, B.S. Cowell, S.A. Hodge, et al., MOX Average Power Early PIE: 8 GWd/MT Final Report, Oak Ridge National Laboratory, ORNL/MD/LTR-172, November 1999.
  • 8
    • 34548126332 scopus 로고    scopus 로고
    • R.N. Morris, C.A. Baldwin, S.A. Hodge, L.J. Ott, C.M. Malone, N.H. Packan, MOX Average Power Intermediate PIE: 21 GWd/MT Final Report, Oak Ridge National Laboratory, ORNL/MD/LTR-199, December 2000.
  • 9
    • 34548119684 scopus 로고    scopus 로고
    • R.N. Morris, C.A. Baldwin, S.A. Hodge, N.H. Packan, MOX Average Power 30 GWd/MT PIE: Final Report, Oak Ridge National Laboratory, ORNL/MD/LTR-212, November 2001.
  • 10
    • 34548139936 scopus 로고    scopus 로고
    • R.N. Morris, C.A. Baldwin, S.A. Hodge, N.H. Packan, MOX Average Power 40 GWd/MT PIE: Final Report, Oak Ridge National Laboratory, ORNL/MD/LTR-241, vol. 1, August 2003.
  • 11
    • 34548134666 scopus 로고    scopus 로고
    • R.N. Morris, C.A. Baldwin, N.H. Packhan, MOX Test Fuel 50 Wd/MT PIE: Capsules 6 and 12 Final Report, Oak Ridge National Laboratory, ORNL/MD/LTR-279, September 2005.
  • 12
    • 34548142794 scopus 로고    scopus 로고
    • National Academy of Sciences Committee on International Security and Arms, Management and Disposition of Excess Weapons Plutonium, National Academy Press, 1994.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.