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Volumn 227, Issue 1, 2004, Pages 85-96

Quantitative assessment of MCP trip transient in a VVER

Author keywords

[No Author keywords available]

Indexed keywords

CODES (SYMBOLS); FAST FOURIER TRANSFORMS; HYDRAULICS; NUCLEAR POWER PLANTS; PUMPS; SAFETY FACTOR; THERMAL EFFECTS;

EID: 0242692565     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.07.005     Document Type: Article
Times cited : (18)

References (20)
  • 1
    • 0035371640 scopus 로고    scopus 로고
    • Protection against high-energy breaks in WWER power plants
    • Andresen A., Bergmann H., Horstmann R. Protection against high-energy breaks in WWER power plants. Nucl. Eng. Des. 206:2002;119-128.
    • (2002) Nucl. Eng. Des. , vol.206 , pp. 119-128
    • Andresen, A.1    Bergmann, H.2    Horstmann, R.3
  • 2
    • 33845765061 scopus 로고
    • Qualification of the Fast Fourier Transform Based Methodology for the Quantification of Thermal-Hydraulic Code Accuracy
    • University of Pisa, NT 194 (92)
    • Bovalini, R., D'Auria, F., Leonardi, M., 1992. Qualification of the Fast Fourier Transform Based Methodology for the Quantification of Thermal-Hydraulic Code Accuracy. DCMN Report, University of Pisa, NT 194 (92).
    • (1992) DCMN Report
    • Bovalini, R.1    D'Auria, F.2    Leonardi, M.3
  • 5
    • 0346291033 scopus 로고    scopus 로고
    • Fast Fourier transform based method for quantitative assessment of code predictions of experimental data
    • American Nuclear Society, Washington
    • D'Auria, F., Mavko, B., Prošek, A., 2000. Fast Fourier transform based method for quantitative assessment of code predictions of experimental data. In: Proceedings of the International Conference BE-2000. American Nuclear Society, Washington.
    • (2000) Proceedings of the International Conference , vol.BE-2000
    • D'Auria, F.1    Mavko, B.2    Prošek, A.3
  • 10
    • 4243475191 scopus 로고    scopus 로고
    • Validation of Computational Models for RELAP5/Mod3.2.2 Using Selected Measured Data from NPP
    • Klepáč, J., et al., 2001. Validation of Computational Models for RELAP5/Mod3.2.2 Using Selected Measured Data from NPP. VÚJE Trnava Report.
    • (2001) VÚJE Trnava Report
    • Klepáč, J.1
  • 12
    • 0036467802 scopus 로고    scopus 로고
    • On the automated assessment of nuclear reactor systems code accuracy
    • Kunz R.F., Kasamala R.F., Mahaffy J.H., Murray C.H. On the automated assessment of nuclear reactor systems code accuracy. Nucl. Eng. Des. 211:2002;245-272.
    • (2002) Nucl. Eng. Des. , vol.211 , pp. 245-272
    • Kunz, R.F.1    Kasamala, R.F.2    Mahaffy, J.H.3    Murray, C.H.4
  • 14
    • 0031245970 scopus 로고    scopus 로고
    • Determination of code accuracy in predicting small-break LOCA experiment
    • Mavko B., Prošek A., D'Auria F. Determination of code accuracy in predicting small-break LOCA experiment. Nucl. Technol. 120:1997;1-19.
    • (1997) Nucl. Technol. , vol.120 , pp. 1-19
    • Mavko, B.1    Prošek, A.2    D'auria, F.3
  • 17
    • 0242491373 scopus 로고    scopus 로고
    • Accuracy assessment of IAEA-SPE-4 predictions with improved FFTBM
    • Prošek A. Accuracy assessment of IAEA-SPE-4 predictions with improved FFTBM. Trans. Am. Nucl. Soc. 87:2002;199-201.
    • (2002) Trans. Am. Nucl. Soc. , vol.87 , pp. 199-201
    • Prošek, A.1
  • 19
    • 0036706457 scopus 로고    scopus 로고
    • Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM)
    • Prošek A., D'Auria F., Mavko B. Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM). Nucl. Eng. Des. 217:2002;179-206.
    • (2002) Nucl. Eng. Des. , vol.217 , pp. 179-206
    • Prošek, A.1    D'auria, F.2    Mavko, B.3
  • 20
    • 0032205848 scopus 로고    scopus 로고
    • The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis
    • Wilson G.E., Boyack B.E. The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis. Nucl. Eng. Des. 186:1998;23-37.
    • (1998) Nucl. Eng. Des. , vol.186 , pp. 23-37
    • Wilson, G.E.1    Boyack, B.E.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.