Results 21 to 30 of about 146 (74)
Data for: Application of ADVANTG to the JET3 - NEXP streaming benchmark experiment
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
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]
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]
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]
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
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
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
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
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]
Luís R +13 more
europepmc +1 more source

