Comparison of the JEFF3. 3 and ENDF/BVII. 1 libraries for SCALE calculations

J Valluš, J Lüley, B Vrban, Š Čerba… - AIP Conference …, 2024 - pubs.aip.org
The use of different neutron cross-section libraries may yield different results in calculations
of multiplication coefficient of the same reactor core configuration. Each cross-section library …

[PDF][PDF] D. 5.2 Report on ESFR, MYRRHA, and ALFRED sensitivity and impact studies. docx

P Romojaro - roma.sckcen.be
S/U analysis have been performed for the ESFR, ASTRID and ALFRED advanced reactor
systems and the multi-purpose flexible irradiation facility MYRRHA, with SCALE, Serpent 2 …

Cross-Section Induced Uncertainties in Neutron Source Emission Rate Calculations

J Lüley, B Vrban, Š Čerba, V Filová, V Nečas… - 2023 - inis.iaea.org
Analysis presented in the paper is focused on the characterization of uncertainties induced
by cross-section data, which contributing to the overall uncertainty of the correction factors …

[PDF][PDF] HORIZON 2020 RESEARCH AND INNOVATION FRAMEWORK PROGRAMME OF THE EUROPEAN ATOMIC ENERGY COMMUNITY

L Fiorito, A Hernandez-Solis, P Romojaro - sanda-nd.eu
The MCNP neutronics model referring to the MYRRHA reactor design version 1.8 was
homogenized at the assembly level as a part of the SANDA WP5. The model description …

[PDF][PDF] CAPACIDADES DEL SISTEMA DE CÓDIGOS SCALE PARA EL ANÁLISIS DE REACTORES RÁPIDOS AVANZADOS

El sistema de códigos SCALE, desarrollado por Oak Ridge National Laboratory (ORNL), se
presenta como una potente herramienta para el estudio de la física de reactores gracias a …