Development of a 3D thermohydraulic-neutronic coupling model for accident analysis in research miniature neutron source reactor (MNSR)

Author:

Ahmadi M.,Rabiee A.,Pirouzmand A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference29 articles.

1. Neutronics-design modification of the Syrian miniature neutron source reactor;Khamis;Prog. Nucl. Energy,2000

2. November). Safety analysis of MNSR reactor during reactivity insertion accident using the validated code PARET;Hainoun,2007

3. Modeling the reactor core of MNSR to simulate its dynamic behavior using the code PARET (No. AECS-NE/RSS--549);Hainoun,2004

4. Thermal-hydraulic and safety aspects of UO2 fuel for low-power reactors;Albarhoum;Prog. Nucl. Energy,2011

5. Thermal–hydraulics features of the use of LEU U3Si2 fuel in low-power reactors;Albarhoum;Ann. Nucl. Energy,2010

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