MCNP-GO: A Python package for assembling MCNP input files with a systems engineering approach
Nuclear Engineering and TechnologyThis article introduces MCNP-GO (https://github.com/afriou/mcnpgo), an open-source Python package designed to manipulate and assemble MCNP input files, allowing users to assemble a set of independent objects, each described by a valid MCNP file, into a ...
A. Friou
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SCIENTIFIC WORKFLOWS FOR MCNP6 AND PROTEUS WITHIN THE NEAMS WORKBENCH [PDF]
EPJ Web of Conferences, 2021 In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling and Simulation (NEAMS)Workbench.
Dominesey Kurt A. +3 more
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THE DOUNREAY FAST REACTOR VAULT CHARACTERISATION USING THE MONTE CARLO N-PARTICLE CODE AS A TOOL TO SUPPORT DECOMMISSIONING PLANNING [PDF]
EPJ Web of Conferences, 2021 A combined empirical and theoretical characterisation approach was taken in order to investigate the activity distribution and inventory in the Dounreay Fast Reactor (DFR) vault, so as to aid with the decommissioning and waste management strategy of the ...
Baldioli Vittoria +3 more
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CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2021 Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation.
Fausser Clément +18 more
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COMPARISON OF WASTE DUE TO IRRADIATED STEELS IN THE ESFR AND DEMO [PDF]
EPJ Web of Conferences, 2021 For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design.
Reid Jack +4 more
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Industria: Jurnal Teknologi dan Manajemen Agroindustri, 2021 Activated charcoal and imarsil (local adsorbent) had shown significant Aflatoxin (AF) decontamination potentials in vegetable oil at a low AF contamination level of ≤ 9 ng/L.
Oluyinka Eunice Aringbangba +4 more
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BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS [PDF]
EPJ Web of Conferences, 2021 Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, including, shielding, material lifetime and remote maintenance ...
Valentine A. +3 more
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Evaluation of mass attenuation coefficient of concrete sample for different traits
Brazilian Journal of Radiation Sciences, 2022 Concrete is widely used in the world and is the main material for civil construction. Due to its properties, it has different uses such as structural, filling and shielding. The aim of this work is to compare experimental and theoretical mass attenuation
Luan Ferreira Bastos +7 more
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Validation of Neutron Evaluated Data Based on The Experimental Reactivity Worth of Tungsten Target in CiADS [PDF]
EPJ Web of Conferences, 2020 Measurement of a cylindrical tungsten target reactivity worth has been performed on the light water zero-power reactor of VENUS-II at China Institute of Atomic Energy (CIAE) in order to verify the neutron evaluated data related to the engineering design ...
Jiang Wei +8 more
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Analysis of the Signal over Noise Ratio of the hodoscope determined by Monte Carlo calculation [PDF]
EPJ Web of Conferences, 2021 The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA) for the purpose of the CABRI International Program (CIP), managed by IRSN in the ...
Di Salvo J., Mirotta S., Chevalier V.
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