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Comparison of the JEFF3. 3 and ENDF/BVII. 1 libraries for SCALE calculations
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 …
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 …
systems and the multi-purpose flexible irradiation facility MYRRHA, with SCALE, Serpent 2 …
Cross-Section Induced Uncertainties in Neutron Source Emission Rate Calculations
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 …
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 …
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
A JIMÉNEZ-CARRASCOSA, N GARCÍA-HERRANZ… - revistanuclear.es
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 …
presenta como una potente herramienta para el estudio de la física de reactores gracias a …