Comparison between Best-Estimate–Plus–Uncertainty Methods and Conservative Tools for Nuclear Power Plant Licensing

Author:

Bucalossi Andrea1,Petruzzi Alessandro2,Kristof Marian3,D’Auria Francesco2

Affiliation:

1. European Commission, Joint Research Center, Institute for Energy Petten, The Netherlands

2. University of Pisa, Nuclear Research Group of San Piero a Grado Via Livornese 1291, San Piero a Grado, Pisa, Italy

3. AiNS, Na hlinách 51, 917 01 Trnava, Slovakia

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference23 articles.

1. “Accident Analysis for Nuclear Power Plants,” IAEA Safety Reports Series, No. 23, International Atomic Energy Agency (2002).

2. “Separate Effects Test Matrix for Thermal-Hydraulic Code Validation,” Vol.1, “Phenomena Characterisation and Selection of Facilities and Tests,” NEA/CSNI/R(93)14/Part.1/Rev., Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1993).

3. “Separate Effects Test Matrix for Thermal-Hydraulic Code Validation,” Vol.2, “Facility and Experimental Characteristics,” NEA/CSNI/R(93)14/Part.2/Rev., Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1993).

4. N. AKSAN et al. “Code Validation Matrix of Thermal-Hydraulic Codes for LWR LOCA and Transients,” CSNI Report No. 132, Committee on the Safety of Nuclear Installations (1987).

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