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Volumn 34, Issue 3, 2007, Pages 233-240

Adaptive fuzzy system for fuel rod cladding failure in nuclear power plant

Author keywords

[No Author keywords available]

Indexed keywords

ADAPTIVE CONTROL SYSTEMS; CONFORMAL MAPPING; FUZZY INFERENCE; NUCLEAR FUEL CLADDING; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS;

EID: 33847609318     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2006.11.012     Document Type: Article
Times cited : (12)

References (14)
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    • Berna, G.A. et al., 1997. FRAPCON-3: a computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup. NUREG/CR-6534 (PNNL-11513), vol. 2, Pacific Northwest National Laboratory, Richland, Washington.
  • 2
    • 33847632614 scopus 로고    scopus 로고
    • Cunningham, M.E., Beyer, C.E., Medvedev, P.G., Berna, G.A., 2001. FRAPTAN: A Computer Code for the Transient Analysis of Oxide Fuel Rod, NUREG/CR - 6739, vol. 1, US Nuclear Regulatory Commission.
  • 3
    • 33847648974 scopus 로고    scopus 로고
    • Cunningham, M.E., Beyer, C.E., Panisko, F.E., Medvedev, P.G., Berna, G.A, Scott, H.H., 2001. FRAPTRAN: Integral Assessment, NUREG/CR - 6739, vol. 2, US Nuclear Regulatory Commission.
  • 4
    • 10744221292 scopus 로고    scopus 로고
    • The use of fuzzy logic methodology to establish inservice inspection priorities for nuclear components
    • Guimarães A.C.F. The use of fuzzy logic methodology to establish inservice inspection priorities for nuclear components. Progress in Nuclear Energy 42-3 (2003) 311-322
    • (2003) Progress in Nuclear Energy , vol.42-3 , pp. 311-322
    • Guimarães, A.C.F.1
  • 5
    • 0037404914 scopus 로고    scopus 로고
    • A new methodology for the study of FAC phenomenon based on a fuzzy rule system
    • Guimarães A.C.F. A new methodology for the study of FAC phenomenon based on a fuzzy rule system. Annals of Nuclear Energy 30-7 (2003) 853-864
    • (2003) Annals of Nuclear Energy , vol.30-7 , pp. 853-864
    • Guimarães, A.C.F.1
  • 6
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    • Effects analysis fuzzy inference system in nuclear problems using approximate reasoning
    • Guimarães A.C.F., and Lapa C.M.F. Effects analysis fuzzy inference system in nuclear problems using approximate reasoning. Annals of Nuclear Energy 31-1 (2004) 107-115
    • (2004) Annals of Nuclear Energy , vol.31-1 , pp. 107-115
    • Guimarães, A.C.F.1    Lapa, C.M.F.2
  • 7
    • 17744410571 scopus 로고    scopus 로고
    • Fuzzy inference system for evaluating and improving nuclear power plant operating performance
    • Guimarães A.C.F., and Lapa C.M.F. Fuzzy inference system for evaluating and improving nuclear power plant operating performance. Annals of Nuclear Energy 31-3 (2004) 311-322
    • (2004) Annals of Nuclear Energy , vol.31-3 , pp. 311-322
    • Guimarães, A.C.F.1    Lapa, C.M.F.2
  • 8
    • 0031198473 scopus 로고    scopus 로고
    • Signal validation using an adaptive neural fuzzy inference system
    • Hines J.W., Wrest D.J., and Uhrig R.E. Signal validation using an adaptive neural fuzzy inference system. Nuclear Technology 119 (1997) 181-193
    • (1997) Nuclear Technology , vol.119 , pp. 181-193
    • Hines, J.W.1    Wrest, D.J.2    Uhrig, R.E.3
  • 9
    • 33847639424 scopus 로고    scopus 로고
    • Hohorst, J.K., 1990. SCDAP/RELAP5/MOD2 Code Manual, vol. 4: MATPRO - A Library of Materials Properties for Light-Water-Reactor Accident Analysis. NUREG/CR-5273 (EGG-2555), vol. 4, EG&G Idaho, Inc., Idaho Falls, Idaho.
  • 10
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    • MatLab 6, 2000. User's Guide of the Fuzzy Logic Toolbox.
  • 11
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    • Siefken, L.J. et al., 1981. FRAP-T6: A Computer Code for the Transient Analysis of Oxide Fuel Rods. NUREG/CR-2148 (EGG-2104), EG&G Idaho, Inc., Idaho Falls, Idaho.
  • 12
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    • Siefken, L.J. et al., 1983. FRAP-T6: A Computer Code for the Transient Analysis of Oxide Fuel Rods. NUREG/CR-2148 Addendum (EGG-2104 Addendum), EG&G Idaho, Inc., Idaho Falls, Idaho.
  • 13
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  • 14
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    • (1985) IEEE Transactions on Systems Man and Cybernetics , vol.SMC-15 , Issue.1 , pp. 116-132
    • Takagi, T.1    Sugeno, M.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.