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1. Target Accuracy Requirements Exercise within WPEC/SG46 and Feedback on Nuclear Data Needs

2. Nuclear data analyses for improving the safety of advanced lead-cooled reactors

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3. Assessment of Decommissioning Cost of Proton Therapy Centers Depending on the Shielding Material in the Building Process

4. Neutron-induced nuclear data for the MYRRHA fast spectrum facility

8. Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference

10. Development and application in multiscale and multiphysics methodologies in Spain: present and future trends

11. Estudio del reactor rápido experimental japonés JOYO

12. Sensitivity and Uncertainty Analyses for Advanced Nuclear Systems (ALFRED, ASTRID, ESFR And MYRRHA)

16. Aprendizaje deslocalizado y nuevas metodologías docentes en el proyecto europeo GREaT PIONEeR

17. Superphénix Benchmark Part I: Results of Static Neutronics

22. Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

23. Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

24. Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients

25. Diagnosis of the unresolved domain treatment in Monte Carlo transport calculations through the identification and modelling of criticality safety experiments

26. Evaluación neutrónica del reactor rápido de sodio ESFR-SMART con combustible modificado y basado en torio

27. About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors

28. Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months

29. Use of similarity indexes to identify spatial correlations of sodium voidreactivity coefficients

30. Detección por Termoluminiscencia de Alimentos Irradiados

31. Results for Exercise I-3 with COBAYA: Analysis of the peaking power factors

32. Validation of COBAYA4/CTF coupling within European NURESIM Platform against MCNP/CTF

33. Overview of the UPM-CSN Activities for Uncertainty Quantification in PWR Full Core Simulations

34. Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor

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

36. Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations

37. Neutron-induced nuclear data for the MYRRHA fast spectrum facility

38. Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

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

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

41. Herramienta Ndast para análisis de sensibilidad e incertidumbre. Aplicación al reactor rápido refrigerado por plomo Alfred

42. Spanish contribution in the design of the ASTRID reactor inside the ESNII+ Project

43. Impact of nuclear data uncertainties on the reactivity of an astrid-like sodium fast reactor

44. Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference

45. Efectos de generación y optimización de librerías de secciones eficaces en el análisis de transitorios en reactores PWR

46. Sensitivity/Uncertainty Analysis for BWR Configurations of Exercise I-2 of UAM Benchmark

47. Desarrollo de una herramienta de verificación para cálculos de difusión mediante COBAYA

50. Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project