Nuclear Engineering and Technology

  • 제38권1호
  • /
  • Pages.11-32
  • /
  • 2006
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

STATE OF THE ART IN USING BEST ESTIMATE CALCULATION TOOLS IN NUCLEAR TECHNOLOGY

  • D'AURIA FRANCESCO (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa) ;
  • ANIS BOUSBIA-SALAH (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa) ;
  • PETRUZZI ALESSANDRO (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa) ;
  • NEVO ALESSANDRO DEL (Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione. Universita di Pisa)
  • 발행 : 2006.02.01
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초록

System thermal-hydraulic codes have been used in the past decades in the areas of design, operation, licensing and safety of Nuclear Power Plants (NPPs). The development and validation of these codes have reached a high degree of maturity, through the consideration of huge experiments and advanced numerical models. Nowadays, the analyses are based upon realistic approaches rather than the conservative evaluation models. However the applications of these computational tools require preliminary qualification issues. Although huge amounts of financial and human resources have been invested for the development and improvement of codes, the calculation results are still affected by errors. In the sophisticated nuclear technology, design and safety of NPP, these errors must be quantified. An overview of the state of the art of the current thermal-hydraulic system code is developed and the need of uncertainty analysis in code calculations is emphasized. Several sources of uncertainty have been classified and commented, and typical applications of such methods are shown.

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참고문헌

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