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Volumn 235, Issue 2-4, 2005, Pages 521-540

Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients

Author keywords

[No Author keywords available]

Indexed keywords

NEUTRON KINETICS; THERMAL-HYDRAULIC SYSTEM CODES; VVER PLANT TRANSIENTS;

EID: 19944428294     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.09.003     Document Type: Conference Paper
Times cited : (18)

References (12)
  • 1
    • 0005691610 scopus 로고
    • An overview of the code scaling, applicability and uncertainty evaluation methodology
    • B.E. Boyack An overview of the code scaling, applicability and uncertainty evaluation methodology Nucl. Eng. Des. 119 1 1990 1
    • (1990) Nucl. Eng. Des. , vol.119 , Issue.1 , pp. 1
    • Boyack, B.E.1
  • 4
    • 0033100741 scopus 로고    scopus 로고
    • Sensitivity analysis in the context of uncertainty analysis for computationally intensive models
    • E. Hofer Sensitivity analysis in the context of uncertainty analysis for computationally intensive models Comput. Phys. Commun. 117 1999 21 34
    • (1999) Comput. Phys. Commun. , vol.117 , pp. 21-34
    • Hofer, E.1
  • 5
    • 0009448928 scopus 로고
    • A software system for probabilistic uncertainty and sensitivity analysis of results from computer models
    • San Diego, CA, USA, 20-25 March
    • B. Krzykacz, E. Hofer, and M. Kloos A software system for probabilistic uncertainty and sensitivity analysis of results from computer models Proceedings of PSAM II San Diego, CA, USA, 20-25 March 1994
    • (1994) Proceedings of PSAM II
    • Krzykacz, B.1    Hofer, E.2    Kloos, M.3
  • 11
    • 20444456588 scopus 로고    scopus 로고
    • Validation of coupled neutronics/thermal hydraulics codes for VVER research reactors (VALCO)
    • Luxembourg, 10-13 November
    • F.P. Weiß Validation of coupled neutronics/thermal hydraulics codes for VVER research reactors (VALCO) FISA-2003, EU Research in Reactor Safety Luxembourg, 10-13 November 2003
    • (2003) FISA-2003, EU Research in Reactor Safety
    • Weiß, F.P.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.