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Volumn 240, Issue 6, 2010, Pages 1443-1449

On the stability of the point reactor kinetics equations

Author keywords

[No Author keywords available]

Indexed keywords

BIBO STABILITY; INTRINSIC STABILITY; LYAPUNOV; NEUTRONICS; POINT REACTOR KINETICS; REACTIVITY FEEDBACK; REACTOR PHYSICS; SIMPLE MODEL; STABILITY DESIGN;

EID: 77950945984     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.03.007     Document Type: Article
Times cited : (21)

References (18)
  • 1
    • 68749104345 scopus 로고    scopus 로고
    • Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing corewide and regional modes of oscillations
    • Doutta G., and Doshi J. Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing corewide and regional modes of oscillations. Progress in Nuclear Energy 51 8 (2009)
    • (2009) Progress in Nuclear Energy , vol.51 , Issue.8
    • Doutta, G.1    Doshi, J.2
  • 4
    • 0345035220 scopus 로고    scopus 로고
    • A moving-boundary nodal model for the analysis of the stability of boiling channels
    • Garea V., Drew D., and Lahey R.T. A moving-boundary nodal model for the analysis of the stability of boiling channels. International Journal of Heat and Mass Transfer 42 19 (1999)
    • (1999) International Journal of Heat and Mass Transfer , vol.42 , Issue.19
    • Garea, V.1    Drew, D.2    Lahey, R.T.3
  • 11
    • 0021531950 scopus 로고
    • NUFREQ-NP: a computer code for the stability analysis of boiling water nuclear reactors
    • Peng S., Becker M., Lahey R.T., and Podowski M. NUFREQ-NP: a computer code for the stability analysis of boiling water nuclear reactors. Nuclear Science and Engineering 88 3 (1984)
    • (1984) Nuclear Science and Engineering , vol.88 , Issue.3
    • Peng, S.1    Becker, M.2    Lahey, R.T.3    Podowski, M.4
  • 13
    • 33845657364 scopus 로고    scopus 로고
    • Use of coupled code technique for best estimate safety analysis of nuclear power plants
    • Salah A.B., and D'Auria F. Use of coupled code technique for best estimate safety analysis of nuclear power plants. Progress in Nuclear Energy 49 1 (2007)
    • (2007) Progress in Nuclear Energy , vol.49 , Issue.1
    • Salah, A.B.1    D'Auria, F.2
  • 14
    • 56949104484 scopus 로고    scopus 로고
    • Application of coupled code method for the analysis of VVER-1000 coolant transient benchmark
    • Salah A.B., and D'Auria F. Application of coupled code method for the analysis of VVER-1000 coolant transient benchmark. Progress in Nuclear Energy 51 1 (2009)
    • (2009) Progress in Nuclear Energy , vol.51 , Issue.1
    • Salah, A.B.1    D'Auria, F.2
  • 18
    • 0141951954 scopus 로고    scopus 로고
    • Safety design maps: an early evaluation of safety to support reactor design
    • Zanocco P., Giménez M., and Delmastro D. Safety design maps: an early evaluation of safety to support reactor design. Nuclear Engineering and Design 225 2-3 (2003)
    • (2003) Nuclear Engineering and Design , vol.225 , Issue.2-3
    • Zanocco, P.1    Giménez, M.2    Delmastro, D.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.