Results 51 to 60 of about 146 (74)
Application of ADVANTG to the JET3 – NEXP streaming benchmark experiment
Fusion Engineering and Design, 2019 Abstract An application of the ADVANTG (AutomateD VAriaNce reducTion Generator) code, which combines the Denovo deterministic transport solver with the MCNP (Monte Carlo N-Particle) Monte Carlo code, to the JET3-NEXP (Joint European Torus work package 3) streaming benchmark experiment is presented in this paper.
Rosaria Villari +2 more
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The viability of ADVANTG deterministic method for synthetic radiography generation
Computer Physics Communications, 2018 Abstract Fast simulation techniques to generate synthetic radiographic images of high resolution are helpful when new radiation imaging systems are designed. However, the standard stochastic approach requires lengthy run time with poorer statistics at higher resolution.
Hyoung K Lee
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Validation and evaluation of the ADVANTG hybrid code on the ICSBEP labyrinth benchmark experiment
Annals of Nuclear Energy, 2018 Abstract Validation and evaluation of the recently released ADVANTG code is presented in the paper. ADVANTG is a hybrid transport code, which combines a deterministic neutron transport code Denovo with MCNP, a well-known Monte Carlo (MC) transport code.
Bor Kos, Domen Kotnik, Luka Snoj
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Comparison of CADIS Implementations in Attila4MC and ADVANTG
Transactions of the American Nuclear Society - Volume 123, 2020 John Brogan +2 more
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Validation and evaluation of the ADVANTG code on the ICSBEP skyshine benchmark experiment
Annals of Nuclear Energy, 2019Abstract Validation and evaluation of the recently released ADVANTG code, which combines a well-known Monte Carlo (MC) transport code MCNP with a deterministic neutron transport code Denovo, is presented in the paper. The aim of ADVANTG is to automate the process of generating the variance reduction parameters for the fixed source MCNP calculations ...
Bor Kos, Domen Kotnik, Luka Snoj
exaly +2 more sources
Nuclear Engineering and Design, 2020
Abstract This paper deals with the self-shielding correction calculation for natural and 40% enriched uranium foils activated in a fast-epithermal neutron field in the MARK III converter of the BR1 research reactor. Although the irradiated uranium foils are thin (~70 μm to 90 μm), neutron self-shielding is not negligible.
Gert Van den Eynde +2 more
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Abstract This paper deals with the self-shielding correction calculation for natural and 40% enriched uranium foils activated in a fast-epithermal neutron field in the MARK III converter of the BR1 research reactor. Although the irradiated uranium foils are thin (~70 μm to 90 μm), neutron self-shielding is not negligible.
Gert Van den Eynde +2 more
exaly +2 more sources
Application of ADVANTG Code for the SDDR Calculations on IFMIF-DONES Target Assembly and HFTM
IEEE Transactions on Nuclear Science, 2022Andrius Tidikas, Gediminas Stankūnas
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Assessment of Skyshine in DEMO Using ADVANTG Code
International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022Christian Bachmann, Bor Kos, Luka Snoj
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Application of ADVANTG variance reduction parameters with MCNP6 at ESS
Journal of Neutron Research, 2020Monte Carlo radiation transport codes have become the primary tool for shielding and activation analysis at high-powered spallation neutron sources. However, use of these codes to model facilities that have large amounts of shielding requires the use of variance reduction methods.
Miller, Thomas M. +2 more
openaire +1 more source