Villanueva López, José Felipe; Carlos Alberola, Sofía; Sánchez Sáez, Francisco; Martón Lluch, Isabel; Martorell Alsina, Sebastián Salvador(Hindawi Limited, 2017)
[EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) ...
Lorduy, M.; Gallardo Bermell, Sergio; Verdú Martín, Gumersindo Jesús(Elsevier, 2020-09)
[EN] The experiments carried out in test facilities improve knowledge of the phenomena that would occur in a nuclear power plant during an accident, and support the validation of the thermal-hydraulic codes used in the ...
Durante un transitorio de rotura pequeña con pérdida de refrigerante (SBLOCA) la despresurización puede ser tan lenta que retrase la entrada del sistema de acumuladores, siendo necesaria la actuación del sistema de inyección ...
El código termohidráulico TRACE5 se ha utilizado para simular el experimento 3-1,
que se ha realizado en la instalación a escala “Large Scale Test Facility (LSTF)”, en una planta
real. Dicho experimento consiste en una ...
Lorduy, M.; Gallardo Bermell, Sergio; Verdú Martín, Gumersindo Jesús(Elsevier, 2018-07)
[EN] Natural circulation flow capability for removing decay core power has been demonstrated, and several studies have focused on taking advantage of this fact. This work studies the sequence of events that occur during a ...
Sanchez Saez, Francisco; Sánchez Galdón, Ana Isabel; Villanueva López, José Felipe; Carlos Alberola, Sofía; Martorell Alsina, Sebastián Salvador(Elsevier, 2018)
[DE] The safety analysis of nuclear power plant is moving toward a realistic approach in which the simulations performed using best estimate computer codes must be accompanied by an uncertainty analysis, known as the Best ...
Sánchez Sáez, Francisco; Carlos Alberola, Sofía; Villanueva López, José Felipe; Sánchez Galdón, Ana Isabel; Martorell Alsina, Sebastián Salvador(Elsevier, 2017)
[EN] The Nuclear Energy Agency auspices simulation of experiments in different facilities under several programs. One on them consisted of performing a counterpart test between ROSA/LSTF and PKL facilities, with the main ...
[EN] The determination of the probability distribution function (PDF) of uncertain input and model parameters in engineering application codes is an issue of importance for uncertainty quantification methods. One of the ...
Nuclear policies have experienced an important change since Fukushima Daiichi nuclear plant accident and the safety of spent fuels has been in the spot issue among all the safety concerns. At many countries, the spent fuel ...
Carlos Alberola, Sofía; Sánchez Galdón, Ana Isabel; Ginestar Peiro, Damián; Martorell Alsina, Sebastián Salvador(Elsevier, 2013-09)
Nuclear Power Plant safety analysis is mainly based on the use of best estimate (BE) codes that predict the plant behavior under normal or accidental conditions. As the BE codes introduce uncertainties due to uncertainty ...