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Criticality validation of SuperMC with ICSBEP

Annals of Nuclear Energy, 2016
Abstract Monte Carlo transport codes are extensively used in neutronic analysis, especially in criticality safety analysis and shielding analysis. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a CAD based Monte Carlo program for integrated simulation of nuclear systems.
Binhang Zhang   +4 more
openaire   +1 more source

SuperMC cloud for nuclear design and safety evaluation

Annals of Nuclear Energy, 2019
Abstract For nuclear design and safety evaluation, along with the development of accuracy and efficiency, further demands are proposed for the nuclear simulation to computing platforms, such as convenient large data processing, secured data storage and transfer as well as secured control over the accessing to the codes.
Liqin Hu   +15 more
openaire   +1 more source

Benchmarking of CAD-based SuperMC with ITER benchmark model

Fusion Engineering and Design, 2014
Abstract Neutronics design and analysis of fusion reactors is significantly complex mainly on geometry and physical process of neutron. The great challenges brought by advanced nuclear energy system promote the development of Super Monte Carlo Calculation Program for Nuclear and Radiation Process (SuperMC).
Jing Song   +4 more
openaire   +1 more source

Validation of SuperMC with BEAVRS benchmark at hot zero power condition

Annals of Nuclear Energy, 2018
Abstract SuperMC is a general, intelligent, accurate and precise simulation software system for the nuclear design and safety evaluation of nuclear systems. In this study, the latest version of SuperMC has been validated by Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS), which is a full-core commercial Westinghouse PWR core ...
Zhiyan Wang   +4 more
openaire   +1 more source

Neutronics Benchmark of CEFR Start-up Tests with SuperMC

Transactions of the American Nuclear Society - Volume 122, 2020
B. Chang, B. Li, Y. Sun, B. Wu, Q. Yang
openaire   +1 more source

Development of Coupled Monte Carlo Transport-burnup and CFD Simulations in SuperMC

Transactions of the American Nuclear Society - Volume 122, 2020
P. Long, L. Wang, B. Wu, L. Yu, S. Yu
openaire   +1 more source

Benchmarking of Super Monte Carlo Simulation Program SuperMC 2

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
Jing Song   +19 more
openaire   +1 more source

Neutronic and Safety Analysis of CAREM-25 Small Modular Reactor Using Supermc Advanced Code

2023
Zare Ganjaroodi, Saeed   +4 more
openaire   +1 more source

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