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Volumn 51, Issue 8, 2009, Pages 769-787

Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing core-wide and regional modes of oscillations

Author keywords

Boiling water reactor; In phase and out of phase oscillations; Nuclear coupled thermal hydraulic model

Indexed keywords

ADVERSE EFFECT; CORE NEUTRONS; DENSITY WAVES; FEEDBACK EFFECTS; HEAT CONDUCTION MODELS; IN-PHASE; IN-PHASE AND OUT-OF-PHASE OSCILLATIONS; INLET SUBCOOLING; INTEGRATED MODELS; NEUTRONICS; NUCLEAR COUPLED THERMAL-HYDRAULIC MODEL; NUMERICAL SIMULATION; NUMERICAL TOOLS; OPERATIONAL TRANSIENTS; OUT OF PHASE; PARAMETRIC STUDY; PRIMARY CIRCUITS; REACTIVITY FEEDBACK; RESEARCH FACILITIES; STABILITY ANALYSIS; STRONG NONLINEAR COUPLING; THERMAL HYDRAULICS; THERMAL-HYDRAULIC MODEL; TIME DOMAIN; WORKING CONDITIONS;

EID: 68749104345     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2009.04.005     Document Type: Article
Times cited : (21)

References (23)
  • 1
    • 0018056071 scopus 로고
    • On the development of methods for analysing transient flow-boiling
    • Banerjee S., and Hancox W.T. On the development of methods for analysing transient flow-boiling. Int. J. Multiphase Flow 4 (1978) 437-460
    • (1978) Int. J. Multiphase Flow , vol.4 , pp. 437-460
    • Banerjee, S.1    Hancox, W.T.2
  • 3
    • 0022723213 scopus 로고
    • Sports - a simple non-linear thermal hydraulic stability code
    • Chatoorgoon V. Sports - a simple non-linear thermal hydraulic stability code. Nuclear Engineering and Design 93 (1986) 51-67
    • (1986) Nuclear Engineering and Design , vol.93 , pp. 51-67
    • Chatoorgoon, V.1
  • 4
    • 0001295106 scopus 로고
    • The analysis of periodic and strange attractors during density-wave oscillations in boiling flows
    • Clausse A., and Lahey Jr. R.T. The analysis of periodic and strange attractors during density-wave oscillations in boiling flows. Chaos, Solitons and Fructals 1 2 (1991) 167-178
    • (1991) Chaos, Solitons and Fructals , vol.1 , Issue.2 , pp. 167-178
    • Clausse, A.1    Lahey Jr., R.T.2
  • 5
    • 68749088756 scopus 로고    scopus 로고
    • D'Auria, F. (Project Coordinator), 2004. Neutronics/Thermal-hydraulics Coupling in LWR Technology, 2, CRISSUE-S WP2: State-of-the-Art Report, OECD/NEAN. 5436.
    • D'Auria, F. (Project Coordinator), 2004. Neutronics/Thermal-hydraulics Coupling in LWR Technology, vol. 2, CRISSUE-S WP2: State-of-the-Art Report, OECD/NEAN. 5436.
  • 8
    • 68749118586 scopus 로고    scopus 로고
    • Dutta, G., 2008 (July). A numerical investigation of nuclear coupled density wave oscillations in a boiling water reactor. Fourth Year Annual Progress Report (unpublished), Department of Mechanical Engineering, Indian Institute of Technology, Bombay.
    • Dutta, G., 2008 (July). A numerical investigation of nuclear coupled density wave oscillations in a boiling water reactor. Fourth Year Annual Progress Report (unpublished), Department of Mechanical Engineering, Indian Institute of Technology, Bombay.
  • 9
    • 68749101036 scopus 로고    scopus 로고
    • Development of characteristics based finite difference implicit scheme to analyze a boiling channel in nuclear reactors
    • Hyderabad, India
    • Dutta, G. and Doshi, J.B., 2008a. Development of characteristics based finite difference implicit scheme to analyze a boiling channel in nuclear reactors. 19th National and 8th ISHMT-ASME Conference at JNTU Hyderabad, India, 1-8 (C193).
    • (2008) 19th National and 8th ISHMT-ASME Conference at JNTU , Issue.C193 , pp. 1-8
    • Dutta, G.1    Doshi, J.B.2
  • 10
    • 56049093435 scopus 로고    scopus 로고
    • A characteristics-based implicit finite-difference scheme for the analysis of instability in water cooled reactors
    • Dutta G., and Doshi J.B. A characteristics-based implicit finite-difference scheme for the analysis of instability in water cooled reactors. Nuclear Engineering and Technology 40 6 (2008) 477-488
    • (2008) Nuclear Engineering and Technology , vol.40 , Issue.6 , pp. 477-488
    • Dutta, G.1    Doshi, J.B.2
  • 11
    • 0018505638 scopus 로고
    • Method of characteristics solutions for non-equilibrium transient flow-boiling
    • Ferch R.L. Method of characteristics solutions for non-equilibrium transient flow-boiling. Int. J. Multiphase Flow 5 (1979) 265-279
    • (1979) Int. J. Multiphase Flow , vol.5 , pp. 265-279
    • Ferch, R.L.1
  • 12
    • 68749097345 scopus 로고
    • NEACRP 3-D LWR Core Transient Benchmark. Final Specifications. NEACRP-L-335
    • Finnemann, H. and Galati, A., 1993. NEACRP 3-D LWR Core Transient Benchmark. Final Specifications. NEACRP-L-335, Revision 1.
    • (1993) Revision , vol.1
    • Finnemann, H.1    Galati, A.2
  • 13
    • 68749098551 scopus 로고    scopus 로고
    • Finnemann, H., Bauer, H., Galati, A. and Martinelli, R., 1993. Results of LWR Core Transient Benchmarks. NEA/NSC/DOC(93)25.
    • Finnemann, H., Bauer, H., Galati, A. and Martinelli, R., 1993. Results of LWR Core Transient Benchmarks. NEA/NSC/DOC(93)25.
  • 14
    • 0033750977 scopus 로고    scopus 로고
    • TRAC-BF1/NEM modeling and results of OECD/NEA BWR core transient benchmarks
    • Fu H., Rodarte J.S., and Ivanov K.N. TRAC-BF1/NEM modeling and results of OECD/NEA BWR core transient benchmarks. Annals of Nuclear Energy 27 (2000) 1051-1058
    • (2000) Annals of Nuclear Energy , vol.27 , pp. 1051-1058
    • Fu, H.1    Rodarte, J.S.2    Ivanov, K.N.3
  • 17
    • 0027866009 scopus 로고
    • Linear modal analysis of out-of-phase instability in boiling water reactor cores
    • Hashimoto K. Linear modal analysis of out-of-phase instability in boiling water reactor cores. Annals of Nuclear Energy 20 12 (1993) 789-797
    • (1993) Annals of Nuclear Energy , vol.20 , Issue.12 , pp. 789-797
    • Hashimoto, K.1
  • 18
    • 0033114908 scopus 로고    scopus 로고
    • A study of boiling water reactor stability behavior
    • Hennig D. A study of boiling water reactor stability behavior. Nuclear Technology 126 (1999) 10-31
    • (1999) Nuclear Technology , vol.126 , pp. 10-31
    • Hennig, D.1
  • 20
    • 0017892285 scopus 로고
    • A semi-implicit method for two-phase fluid dynamics
    • Liles D.R., and Reed W.H. A semi-implicit method for two-phase fluid dynamics. Journal of Computational Physics 26 (1978) 390-407
    • (1978) Journal of Computational Physics , vol.26 , pp. 390-407
    • Liles, D.R.1    Reed, W.H.2
  • 21
    • 0001921715 scopus 로고
    • Coupled thermohydraulic-neutronic instabilities in boiling water nuclear reactors: a review of the state of the art
    • March-Leuba J., and Rey J.M. Coupled thermohydraulic-neutronic instabilities in boiling water nuclear reactors: a review of the state of the art. Nuclear Engineering and Design 145 (1993) 97-111
    • (1993) Nuclear Engineering and Design , vol.145 , pp. 97-111
    • March-Leuba, J.1    Rey, J.M.2
  • 22
    • 0343777398 scopus 로고    scopus 로고
    • Coupling of density wave oscillations in parallel channels with high order modal kinetics; application to BWR out of phase oscillations
    • Munoz-Cobo J.L., Rosello O., Miro R., Escriva A., Ginestar D., and Verdu G. Coupling of density wave oscillations in parallel channels with high order modal kinetics; application to BWR out of phase oscillations. Annals of Nuclear Energy 27 (2000) 1345-1371
    • (2000) Annals of Nuclear Energy , vol.27 , pp. 1345-1371
    • Munoz-Cobo, J.L.1    Rosello, O.2    Miro, R.3    Escriva, A.4    Ginestar, D.5    Verdu, G.6
  • 23
    • 0031553170 scopus 로고    scopus 로고
    • Non-linear dynamics of a two phase flow system in an evaporator: the effects of (i) a time varying pressure drop, (ii) an axially varying heat flux
    • Narayanan S., Srinivas B., Pushpavanan S., and Bhallamudi S.M. Non-linear dynamics of a two phase flow system in an evaporator: the effects of (i) a time varying pressure drop, (ii) an axially varying heat flux. Nuclear Engineering and Design 178 (1997) 279-294
    • (1997) Nuclear Engineering and Design , vol.178 , pp. 279-294
    • Narayanan, S.1    Srinivas, B.2    Pushpavanan, S.3    Bhallamudi, S.M.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.