Results 51 to 60 of about 80 (60)

Reactor pressure vessel damage (dpa/s) calculation and testing of 56Fe data libraries based on PCA benchmark model simulations using the SuperMC 3.4 code

Annals of Nuclear Energy, 2022
Edward Shitsi, Jing Song, Lijuan Hao
exaly  

CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

Annals of Nuclear Energy, 2015
Guangyao Sun, Yican Wu, Lijuan Hao
exaly  

Numerical benchmark of SuperMC3.2 with HCPB mock-up experiment

Fusion Engineering and Design, 2019
Guangyao Sun, Lijuan Hao
exaly  

Radiation Safety Analysis, 2 Models of Industrial Radiography Techniques in Tubes Testing Using SuperMc 3.2

2018
Izadi, Mahdi, Parsaee, Siyamac
openaire   +1 more source

Validation of SuperMC code by simulating a Metal-cooled fast reactor – BFS-62-3A

Annals of Nuclear Energy, 2018
Zeeshan Jamil, Jing Song, Yican Wu
exaly  

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

Journal of Nuclear Engineering and Radiation Science, 2019
Zou J
exaly  

Verification of SuperMC for simulation of a high-dose-rate brachytherapy source

Journal of the Korean Physical Society, 2017
Lijuan Hao
exaly  

Verification of SuperMC with ITER C-Lite neutronic model

Fusion Engineering and Design, 2016
exaly  

Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I

Annals of Nuclear Energy, 2018
exaly  

SuperMC Model of the TRIGA Vienna Reactor and its Confirmation

2019
Nadeem Shaukat, Muhammad Tariq Siddique, Rustam Khan   +2 more
exaly