Results 21 to 30 of about 146 (74)

Data for: Application of ADVANTG to the JET3 - NEXP streaming benchmark experiment

open access: yes, 2019
Final results showing the application of ADVANTG code to a complex neutron streaming problem in a realistic fusion geometry. Results include a comparison of ADVANTG accelerated simulation results to analog results, results from different institutions and
Kos, B
core   +2 more sources

Study on A-FNS shielding analysis with variance reduction parameter generation code

open access: yes, 2023
Design activities of advanced fusion neutron source A-FNS have been conducted to perform the irradiation tests for fusion reactor materials. It is necessary to evaluate the effective dose rate of the lateral access cell in the A-FNS facility by shielding
Ota Masayuki   +4 more
core   +1 more source

Transport Test Problems for Hybrid Methods Development [PDF]

open access: yes, 2011
This report presents 9 test problems to guide testing and development of hybrid calculations for the ADVANTG code at ORNL. These test cases can be used for comparing different types of radiation transport calculations, as well as for guiding the ...
Shaver, Mark W.   +3 more
core   +1 more source

Radiation Detection Computational Benchmark Scenarios [PDF]

open access: yes, 2013
Modeling forms an important component of radiation detection development, allowing for testing of new detector designs, evaluation of existing equipment against a wide variety of potential threat sources, and assessing operation performance of radiation ...
McDonald, Ben S.   +3 more
core   +1 more source

Validation and practical use of the ADVANTG code for neutron and photon particle transport [PDF]

open access: yes, 2019
V magistrskem delu sta predstavljeni validacija in praktična uporaba pred kratkim razvitega programa ADVANTG, ki združuje Monte Carlo transportni program MCNP z determinističnim transportnim programom Denovo.
Kotnik, Domen
core  

Dose Rate Evaluation for the ES-3100 Package with HEU Content Using MCNP, ADVANTG, Monaco, and MAVRIC

open access: yesNuclear Technology, 2018
AbstractThis paper presents a comparative study of dose rate calculations for the ES-3100 package with highly enriched uranium (HEU) content for different source configurations using the following ...
openaire   +4 more sources

An Evolutionary Algorithm for Spatial Discretization Optimization

open access: yes, 2017
A novel evolutionary algorithm for spatial discretization meshing using a Cartesian grid for radiation transport simulations is proposed. The generated Cartesian grid is used by ADVANTG to generate weight windows for MCNP. The algorithm was tested on the
Norris, Edward T.   +3 more
core   +1 more source

Nuclear Data Uncertainty Propagation in Complex Fusion Geometries

open access: yes, 2020
The ASUSD program package was designed to automate and simplify the process of deterministic nuclear data sensitivity and uncertainty quantification.
Sjöstrand, Henrik,   +8 more
core   +1 more source

Data for: Validation and Evaluation of the ADVANTG Code on the ICSBEP Skyshine Benchmark Experiment

open access: yes, 2018
Data for figures 6, 7, 8, 9 and 10.THIS DATASET IS ARCHIVED AT DANS/EASY, BUT NOT ACCESSIBLE HERE.
Snoj, L (via Mendeley Data)
core   +2 more sources

Neutronics Simulations for DEMO Diagnostics. [PDF]

open access: yesSensors (Basel), 2023
Luís R   +13 more
europepmc   +1 more source

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