D. Cuervo

Education and Training of Future Nuclear Engineers Through the use of, an Interactive Plant Simulator

N. García-Herranz, José-María Aragonés, O. Cabellos, 2010 .

Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis

S. Sánchez-Cervera, N. García-Herranz, E. Castro, 2017 .

Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases

M. Avramova, D. Cuervo, M. Avramova, 2013 .

Uncertainty quantification and propagation with probability boxes

D. Cuervo, L. Duran-Vinuesa, D. Cuervo, 2021, Nuclear Engineering and Technology.

Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project

Soeren Kliem, J. J. Herrero, Gonzalo Jimenez, 2015 .

Evaluation and enhancement of COBRA-TF efficiency for LWR calculations

M. Avramova, Kostadin Ivanov, Rafael Miró, 2006 .

Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR

N. García-Herranz, J. J. Herrero, Carol Ahnert, 2012 .