Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
6760056 | Nuclear Engineering and Design | 2016 | 7 Pages |
Abstract
A computer code was established named ET-RR-1-10 to investigate the thermal hydraulic behavior of the ETRR1 (first Egyptian research reactor) research reactor when its power upgraded to 10Â MW using the new fuel plate elements type. The work done include both normal and flow reduction conditions. The code modeled primary loop, secondary lop, and reactor kinetics. All code models used finite difference technique. The code results were tested against the available corresponding experimental data taken from a similar research reactor MITR (Massachusetts Institute of Technology research reactor) for the sake of code validation. The results showed good agreement, and the code can be used for thermal hydraulic calculations.
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Authors
M. El Sayed Mustafa, M. Shaat, M. El Kady,