DATA FOR "Development of a transient neutronics and thermal-hydraulics coupling method for TRIGA reactor"
Abstract
This dataset is derived from the journal article 'Development of a Transient Neutronics and Thermal-Hydraulics Coupling Method for the TRIGA Reactor.' It includes geometric parameters of the TRIGA reactor core, initial operational states, and thermal-hydraulic and neutronics parameters during transient processes.
Fields of Study & Subjects
Nuclear reactor physics and engineering
Nuclear Engineering Thermal-Hydraulics
Nuclear Materials and Properties
Publication details
- Journal / source
- ScienceDB
- Publication date
- 13 January 2026
- Language
- EN
- Document type
- Dataset