Results 61 to 70 of about 220 (75)
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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.
Andrew Bingham, Hyoung K. Lee
openaire   +1 more source

Validation and evaluation of the ADVANTG code on the ICSBEP skyshine benchmark experiment

Annals of Nuclear Energy, 2019
Abstract 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 ...
Kotnik, Domen   +5 more
openaire   +1 more source

ADVANTG hybrid code application for the analysis of neutron field depression in uranium foils activated in the MARK III converter of the BR1 reactor

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.
Yurdunaz Çelik   +4 more
openaire   +1 more source

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.
Kotnik, Domen   +3 more
openaire   +1 more source

Neutron streaming along shielding penetrations of high energy medical accelerators using MCNP and ADVANTG codes

Physica Medica, 2016
Neutron streaming along penetrations in the shielding of high energy medical accelerators may result in an undesirable radiation dose to the personnel of the radiation therapy facility. However, accurate estimation of the neutron dose is generally difficult due to the long neutron paths and complex geometries encountered. Monte Carlo methods have been
I.E. Stamatelatos   +2 more
openaire   +1 more source

The Analysis of the External Neutron Monitor Responses in a Simplified JET-Like Tokamak Using ADVANTG

Fusion Science and Technology, 2017
The application of the Automated Variance Reduction Generator (ADVANTG) code to accelerate MCNP neutron transport calculations in fusion-relevant geometries is presented. The ADVANTG code generates variance-reduction parameters using the Consistent Adjoint Driven Importance Sampling (CADIS) and Forward-Weighted Consistent Adjoint Driven Importance ...
Čufar, Aljaž   +5 more
openaire   +1 more source

Assessment of Skyshine in DEMO Using ADVANTG Code

International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022
Domen Kotnik   +5 more
openaire   +1 more source

Comparison of CADIS Implementations in Attila4MC and ADVANTG

Transactions of the American Nuclear Society - Volume 123, 2020
E. Sosnovsky, J. Kulesza, J. Brogan
openaire   +1 more source

Application of ADVANTG Code for the SDDR Calculations on IFMIF-DONES Target Assembly and HFTM

IEEE Transactions on Nuclear Science, 2022
Gediminas Stankunas, Andrius Tidikas
openaire   +1 more source

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