D. Cuervo

发表

A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides

F. Álvarez-Velarde, F. Martín-Fuertes, N. García-Herranz, 2013 .

INTERFACE DISCONTINUITY FACTORS IN THE MODAL EIGENSPACE OF THE MULTIGROUP DIFFUSION MATRIX

N. García-Herranz, D. Cuervo, J. Herrero, 2011 .

Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators

S. Sánchez-Cervera, N. García-Herranz, D. Cuervo, 2017 .

Uncertainty quantification and propagation with probability boxes

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

Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes

A. Sabater, S. Sánchez-Cervera, N. García-Herranz, 2017 .

Evaluation and enhancement of COBRA-TF efficiency for LWR calculations

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

Testing the NURESIM platform on a PWR main steam line break benchmark

P. Mala, H. Ferroukhi, N. García-Herranz, 2017 .

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 .

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

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

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 .

Effects of cross sections tables generation and optimization on rod ejection transient analyses

S. Sánchez-Cervera, N. García-Herranz, J. J. Herrero, 2014 .