Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code

Subjects

Subjects :

Nuclear and High Energy Physics
ARC fusion reactor
Nuclear Energy and Engineering
Mechanical Engineering
Neutronics
Monte Carlo
Serpent
General Materials Science
Civil and Structural Engineering

Details

ISSN :

19437641 and 15361055

Volume :

78

Database :

OpenAIRE

Journal :

Fusion Science and Technology

Accession number :

edsair.doi.dedup.....1b291dcc8ba3769f529e4647ce353fe3

Full Text :

https://doi.org/10.1080/15361055.2021.2003151