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Volumn 236, Issue 12, 2006, Pages 1240-1255

Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; DATA ACQUISITION; ERROR ANALYSIS; HYDRAULICS; NUCLEAR ENERGY; SENSITIVITY ANALYSIS;

EID: 33646103663     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.11.005     Document Type: Article
Times cited : (13)

References (15)
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    • Bousbia Salah, A., 2004. Overview of coupled system thermal-hydraulic-3D neutron kinetics code applications. Ph.D. Thesis, Ref: 17033. Università di Pisa.
  • 2
    • 20444459538 scopus 로고    scopus 로고
    • Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test
    • Bousbia Salah A., Galassi G.M., D'Auria F., and Končar B. Assessment study of the coupled code RELAP5/PARCS against the Peach Bottom BWR turbine trip test. Nucl. Eng. Des. 235 (2005) 1727-1736
    • (2005) Nucl. Eng. Des. , vol.235 , pp. 1727-1736
    • Bousbia Salah, A.1    Galassi, G.M.2    D'Auria, F.3    Končar, B.4
  • 3
    • 0034249270 scopus 로고    scopus 로고
    • Development of code with capability of internal assessment of uncertainty
    • D'Auria F., and Giannotti W. Development of code with capability of internal assessment of uncertainty. Nucl. Technol. 131 1 (2000) 159-196
    • (2000) Nucl. Technol. , vol.131 , Issue.1 , pp. 159-196
    • D'Auria, F.1    Giannotti, W.2
  • 4
    • 33646113357 scopus 로고    scopus 로고
    • D'Auria, F. (Lead Author), 2004. Neutronics/Thermal-hydraulics Coupling in LWR Technology: State-of-the-art Report (REAC-SOAR). CRISSUE-S-WP2, OCDE/NEA-5436.
  • 5
    • 33646084357 scopus 로고    scopus 로고
    • Downar, T., Lee, D., Xu, Y., Kozlowski, T., 2004. PARCS v2.6: U.S. NRC core neutronics simulator. Theory manual, DRAFT (11/10/04).
  • 6
    • 33646078090 scopus 로고    scopus 로고
    • Fletcher, C.D., Schultz, R.R., 1995. RELAP5/MOD3 Code Manual, vol. IV, User's Guidelines. Idaho National Engineering Laboratory, Idaho Falls, Idaho, NUREG/CR-5536, INEL-95/0174.
  • 7
    • 0004764385 scopus 로고    scopus 로고
    • DYN3D-a 3-dimensional core model for steady state and transient analysis of thermal reactors
    • Mito (Japan), September 16-20
    • Grundmann U., and Rohde U. DYN3D-a 3-dimensional core model for steady state and transient analysis of thermal reactors. International Conference on Physics of Reactors PHYSOR 96. Mito (Japan), September 16-20 (1996)
    • (1996) International Conference on Physics of Reactors PHYSOR 96
    • Grundmann, U.1    Rohde, U.2
  • 8
    • 33646111175 scopus 로고    scopus 로고
    • Ivanov, B., Ivanov, K., 2002. VVER-1000 coolant transient benchmark: phase-1, volume I: final specifications. OECD Paris, NEA/NSC/DOC.
  • 9
    • 33646087651 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.
  • 10
    • 33646121034 scopus 로고    scopus 로고
    • Transient simulations in VVER-1000-comparison between DYN3D-ATHLET and DYN3D-RELAP5
    • Dresden, Germany, September 23-26
    • Kozmenkov Y., et al. Transient simulations in VVER-1000-comparison between DYN3D-ATHLET and DYN3D-RELAP5. AER-Symposium on VVER Physics and Reactor Safety. Dresden, Germany, September 23-26 (2003)
    • (2003) AER-Symposium on VVER Physics and Reactor Safety
    • Kozmenkov, Y.1
  • 11
    • 0009448928 scopus 로고
    • A software system for probabilistic uncertainty and sensitivity analysis of results from computer models
    • San Diego, CA, USA, March 20-25
    • Krzykacz B., Hofer E., and Kloos M. A software system for probabilistic uncertainty and sensitivity analysis of results from computer models. Proceedings of PSAM II. San Diego, CA, USA, March 20-25 (1994)
    • (1994) Proceedings of PSAM II
    • Krzykacz, B.1    Hofer, E.2    Kloos, M.3
  • 14
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    • Weiss, F.P (Lead Author), 2003. Validation of coupled neutronics/thermal hydraulics codes for VVER reactors (VALCO). FISA-2003/EU Research in Reactor Safety. EC Luxembourg, November 10-13.
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    • Wickett, T., D'Auria, F., Glaeser, H., Chojnacki, E., Lage, C., Sweet, D., Neil, A., Galassi, G.M., Belsito, S., Ingegneri, M., Gatta, P., Skorek, T., Hoper, E., Kloos, M., Ounsy, M., Sanchez, J.I., 1998. Report of the uncertainty method study for advanced best estimate therma1hydraulic code applications. OECD/NEA/CSNI R (97) 35, vols. I and II, June.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.