MNSR transient analysis using the RELAP5/Mod3.2 code

MNSR transient analysis using the RELAP5/Mod3.2 code

To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated. The model was verified by comparing the results with the measured and the previously calculated data. The comparisons consisted of comparing th...

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Bibliographic Details
Main Authors: S. Dawahra, K. Khattab, F. Alhabit
Format: Article
Language:English
Published: Elsevier 2020-09-01
Series:Nuclear Engineering and Technology
Subjects:
MNSR
RELAP
MCNP
Transient analyses
Safety
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319308393

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