A complete CFD study on natural convection in the TRIGA Mark II reactor
C Introini, D Chiesa, M Nastasi, E Previtali… - … Engineering and Design, 2023 - Elsevier
This work describes the most complete and up-to-date thermal-hydraulics CFD model for
studying the natural circulation regime within the entire TRIGA Mark II reactor at the …
studying the natural circulation regime within the entire TRIGA Mark II reactor at the …
Validation of the COTENP Code: A Steady‐State Thermal‐Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies
DA Castellanos-Gonzalez, JML Moreira… - … and Technology of …, 2018 - Wiley Online Library
This article presents the validation of the Code for Thermal‐hydraulic Evaluation of Nuclear
Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady‐state …
Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady‐state …
[PDF][PDF] A review of failure modes of nuclear fuel cladding
In this research, an effort has been made to systematically establish the research studies
managed on an assortment of nuclear fuel cladding materials since the initial reactors …
managed on an assortment of nuclear fuel cladding materials since the initial reactors …