1. THERMIC-1H v3.0, A Program for the Calculus and Thermalhydraulic Design of Reactor Cores;Abbate,1995
2. Transient thermal hydraulic analysis of the IAEA 10 MW MTR reactor during loss of flow accident to investigate the flow inversion;AL-Yahia;Ann. Nucl. Energy,2013
3. Transient analyses of the Jordanian 5 MW research reactor under LOEP accident;Al-Yahia;Ann. Nucl. Energy,2016
4. Alnajjar, A., Abushqair, A., Ahmed, F., Aldahyyat, A., Abusaleem, Kh., 2016. Development of level 1 probabilistic safety assessment for Jordan research and training reactor (JRTR) in the framework of IAEA-led competence building project. In: 13th International Conference on Probabilistic Safety Assessment and Management. PSAM 13, 2–7 Oct 2016, Seoul, Korea.
5. Analysis of loss of flow accident resulting from the primary pump shaft break transient of the NUR research reactor;Azzoune;J. Nucl. Sci. Technol.,2019