메뉴 건너뛰기




Volumn 33, Issue 7, 2006, Pages 646-652

Analysis of the Peach Bottom flow stability test number 3 using the coupled RELAP5/PARCS code

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; CODES (STANDARDS); FEEDBACK; HYDRAULICS; NEUTRONS; NUCLEAR POWER PLANTS; STABILITY;

EID: 33646366909     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2006.02.012     Document Type: Article
Times cited : (9)

References (13)
  • 1
    • 33646349127 scopus 로고    scopus 로고
    • Bousbia-Salah, A., 2004. Overview of coupled system thermal-hydraulic 3D neutron kinetic code applications, PhD Thesis, Ref: 17033, Pisa University, Italy.
  • 2
    • 1842611120 scopus 로고    scopus 로고
    • Sensitivity analysis of the Peach Bottom turbine trip 2 experiment
    • Bousbia Salah A., D'Auria F., and Bambara M. Sensitivity analysis of the Peach Bottom turbine trip 2 experiment. Kerntechnik 69 1-8 (2004) 2004
    • (2004) Kerntechnik , vol.69 , Issue.1-8 , pp. 2004
    • Bousbia Salah, A.1    D'Auria, F.2    Bambara, M.3
  • 3
    • 33646371134 scopus 로고    scopus 로고
    • Carmichael, L.A., Niemi, R.O., 1978. Transient and stability tests at peach bottom atomic power station Unit 2 at end of cycle 2, EPRI Report NP-564.
  • 4
    • 33646369286 scopus 로고    scopus 로고
    • D'Auria, F. (Editor), 1997. The State of the Art Report on Boiling Water Reactor Stability. NEA/CSNI/R(96)21.
  • 5
    • 33646363466 scopus 로고    scopus 로고
    • 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.
  • 6
    • 33646373114 scopus 로고    scopus 로고
    • D'Auria, F., Lombardi Costa, A., Bousbia Salah, A., 2005. The boiling water reactor stability. Annex-10 of the IAEA-TECDOC-1474 on Natural Circulation in Water-cooled Nuclear Power Plants Phenomena, Models, and Methodology for System Reliability Assessments, pp. 281-320.
  • 7
    • 33646357376 scopus 로고    scopus 로고
    • Hänggi, P., 2001. Investigating BWR stability with a new linear frequency-domain method and detailed 3D neutronics, PhD Thesis, Swiss Federal Institute of Technology, ETH.
  • 8
    • 0035395406 scopus 로고    scopus 로고
    • BWR regional instability analysis by TRAC/BF1-ENTRÉE-I: application to density-wave oscillation
    • Hotta A., Honma M., Ninokata H., and Matsui Y. BWR regional instability analysis by TRAC/BF1-ENTRÉE-I: application to density-wave oscillation. Nuclear Technology 135 (2001) 1-16
    • (2001) Nuclear Technology , vol.135 , pp. 1-16
    • Hotta, A.1    Honma, M.2    Ninokata, H.3    Matsui, Y.4
  • 10
    • 33646361465 scopus 로고    scopus 로고
    • Joo, H.G., Barber, D., Jiang, G., Downar, T.J., 1998. PARCS, A Multi-Dimensional Two Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal Method, PU/NE-98-26.
  • 11
    • 33646361948 scopus 로고    scopus 로고
    • Maggini, F., 2004. Contributions to study instability in BWR: application to Peach Bottom-2 NPP. Laurea thesis etd-183309, University of Pisa.
  • 12
    • 0036643133 scopus 로고    scopus 로고
    • A nodal modal method for the neutron diffusion equation. Application to BWR instabilities analysis
    • Miró R., Ginestar D., Verdú G., and Hennig D. A nodal modal method for the neutron diffusion equation. Application to BWR instabilities analysis. Annals of Nuclear Energy 29 (2002) 1171-1194
    • (2002) Annals of Nuclear Energy , vol.29 , pp. 1171-1194
    • Miró, R.1    Ginestar, D.2    Verdú, G.3    Hennig, D.4
  • 13
    • 33646347519 scopus 로고    scopus 로고
    • Solis, J., Ivanov, K., Sarikaya, B., Olson, A., Hunt, K.W., 2001. Boiling Water Reactor Turbine Trip (TT) Benchmark, vol. 1. Final Specifications. NEA/NSC/DOC.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.