Adoption of a fast dynamic model to simulate transient operations of MNSR
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Elsevier BV
Reference53 articles.
1. Investigation of natural convection in miniature neutron source reactor of Isfahan by applying the porous media approach;Abbassi;Nucl. Eng. Des.,2016
2. Development of a fast thermal-hydraulic model to simulate heat and fluid flow in MNSR;Abbassi;Ann. Nucl. Energy,2022
3. A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents;Ajami;Prog. Nucl. Energy,2020
4. Coupling of neutronics and thermal-hydraulic codes for simulation of the MNSR reactor;Al Zain;Nucl. Sci. Eng.,2019
5. Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (TH) characteristics of the MNSR research reactor fuel assembly;Al-Zain;Nucl. Eng. Des.,2024
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