Neutronic and thermal–hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core
E. Chham, T. El Bardouni, K. Benaalilou, H. Boukhal, B. El Bakkari, Y. Boulaich, C. El Younoussi, B. Nacir
Abstract
E. Chham, T. El Bardouni, K. Benaalilou, H. Boukhal, B. El Bakkari, Y. Boulaich, C. El Younoussi, B. Nacir
Abstract
An abstract is not available in the OpenAlex record for this paper.
OpenAlex reports 17 citations for this work. Citation counts describe recorded attention and do not establish research quality.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
Key concepts: TRIGA, Research reactor, Nuclear engineering, Neutron flux, Control rod, Thermal hydraulics, Core (optical fiber), Neutron temperature