Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test
暂无分享,去创建一个
Francesc Reventos | J. Freixa | V. Martinez-Quiroga | F. Reventós | J. Freixa | V. Martinez-Quiroga
[1] Francesc Reventos,et al. Analysis of a Main Steam Line Break in Asco Nuclear Power Plant , 2001 .
[2] Francesc Reventos,et al. The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios , 2014 .
[3] Jordi Freixa,et al. Boron Transport Model with Physical Diffusion for RELAP5 , 2007 .
[4] Francesco Saverio D'Auria,et al. Accident Analysis for Nuclear Power Plants , 2002 .
[5] Francesc Reventós. Thermal-Hydraulic Analysis in Support of Plant Operation , 2011 .
[6] Francesc Reventos,et al. Analysis of an actual reactor trip operating event due to a high variation of neutron flux occurring in the Vandellòs-II nuclear power plant , 2010 .
[7] Francesc Reventos,et al. Analysis of a Main-Steam-Line Break in Ascó NPP , 2004 .
[8] Francesc Reventos,et al. Analysis of low load transients for the Vandellòs-II NPP: Application to operation and control support , 2007 .
[9] Francesc Reventos,et al. Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control , 2008 .
[10] Francesco Saverio D'Auria,et al. Scaling in nuclear reactor system thermal-hydraulics , 2010 .
[11] Francesc Reventos,et al. An analytical comparative exercise on the OECD-SETH PKL E2.2 experiment , 2008 .
[12] Francesc Reventos,et al. SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety , 2009 .
[13] Francesc Reventos,et al. Advanced qualification process of ANAV NPP integral dynamic models for supporting plant operation and control , 2007 .
[14] Richard R. Schultz,et al. RELAP5/MOD3 Code Manual , 1992 .