| Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations N Garcia-Herranz, O Cabellos, J Sanz, J Juan, JC Kuijper Annals of Nuclear Energy 35 (4), 714-730, 2008 | 108 | 2008 |
| Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core D Rochman, O Leray, M Hursin, H Ferroukhi, A Vasiliev, A Aures, ... Nuclear Data Sheets 139, 1-76, 2017 | 63 | 2017 |
| The analytic coarse-mesh finite difference method for multigroup and multidimensional diffusion calculations JM Aragonés, C Ahnert, N García-Herranz Nuclear Science and Engineering 157 (1), 1-15, 2007 | 57 | 2007 |
| The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis JA Lozano, N García-Herranz, C Ahnert, JM Aragonés Annals of Nuclear Energy 35 (12), 2365-2374, 2008 | 47 | 2008 |
| Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations P Romojaro, F Álvarez-Velarde, I Kodeli, A Stankovskiy, CJ Díez, ... Annals of Nuclear Energy 101, 330-338, 2017 | 41 | 2017 |
| ACAB Inventory code for nuclear applications: User’s manual V. 2008 J Sanz, O Cabellos, N García-Herranz NEA-1839 6, 475-480, 2008 | 40 | 2008 |
| Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis N García-Herranz, D Cuervo, A Sabater, G Rucabado, ... Nuclear Engineering and Design 321, 38-47, 2017 | 35 | 2017 |
| Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR JJ Herrero, N García-Herranz, D Cuervo, C Ahnert Annals of Nuclear Energy 46, 106-115, 2012 | 32 | 2012 |
| Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference E Castro, C Ahnert, O Buss, N Garcia-Herranz, A Hoefer, D Porsch Annals of Nuclear Energy 95, 148-156, 2016 | 30 | 2016 |
| Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis JA Lozano, J Jiménez, N García-Herranz, JM Aragonés Annals of Nuclear Energy 37 (3), 380-388, 2010 | 30 | 2010 |
| Methods and Results for the MSLB NEA Benchmark using SIMTRAN and RELAP-5 JM Aragones, C Ahnert, O Cabellos, N Garcia-Herranz, ... Nuclear technology 146 (1), 29-40, 2004 | 30 | 2004 |
| Analytic coarse-mesh finite-difference method generalized for heterogeneous multidimensional two-group diffusion calculations N García-Herranz, O Cabellos, JM Aragonés, C Ahnert Nuclear science and engineering 144 (1), 23-35, 2003 | 30 | 2003 |
| Optimization of multidimensional cross-section tables for few-group core calculations S Sánchez-Cervera, N García-Herranz, JJ Herrero, O Cabellos Annals of Nuclear Energy 69, 226-237, 2014 | 26 | 2014 |
| European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients S Bortot, P Sciora, F Alvarez-Velarde, E Fridman, IG Cruzado, NG Herranz, ... ICAPP 2015-International Congress on Advances in Nuclear Power Plants, paper …, 2015 | 24 | 2015 |
| Assessment of fissionable material behaviour in fission chambers O Cabellos, P Fernandez, D Rapisarda, N García-Herranz Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2010 | 23 | 2010 |
| ACAB-2008, ACtivation ABacus Code V2008 J Sanz, O Cabellos, N García-Herranz NEA Data Bank NEA-1839, 2008 | 22 | 2008 |
| Development and Performance of the Analytic Nodal Diffusion SolverANDES'in Multigroups for 3D Rectangular Geometry JA Lozano, JM Aragonés, N García-Herranz TRANSACTIONS-AMERICAN NUCLEAR SOCIETY 97, 696, 2007 | 21 | 2007 |
| On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR P Romojaro, F Álvarez-Velarde, O Cabellos, N García-Herranz, ... Annals of Nuclear Energy 161, 108416, 2021 | 20 | 2021 |
| Sensitivity methods for effective delayed neutron fraction and neutron generation time with summon P Romojaro, F Álvarez-Velarde, N García-Herranz Annals of Nuclear Energy 126, 410-418, 2019 | 20 | 2019 |
| Dependence of the nodal homogenized two-group cross sections on intranodal flux-spectrum, burnup and history N Garcia-Herranz, JM Aragones, O Cabellos, C Ahnert M and C'99-Mathematics and Computation, Reactor Physics and Environmental …, 1999 | 20 | 1999 |
