References
- 1. CIAE. (1993). Safety Analysis Report (SAR) for the Syrian Miniature Neutron Source Reactor. China.
- 2. Khamis, I., & Khattab, K. (1999). Lowering the enrichment of the Syrian Miniature Neutron Source Reactor. Ann. Nucl. Energy, 26, 1031–1036.
- 3. Matos, J., & Lell, R. (2005). Feasibility study on potential LEU fuels for a generic MNSR reactor. In International Meeting on Reduced Enrichment for Research and Test Reactors, November 6–10, 2005. Boston, Massachusetts.
- 4. Briesmeister, F. J. (2000). MCNP4C manual, Monte Carlo N-Particle Transport Code System. (RSICC code package CCC-700/MCNP4C). Oak Ridge National Laboratory, TN, and DOE, USA.
- 5. Jonah, S. A., Liaw, J. R., & Matos, J. E. (2007). Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1). Ann. Nucl. Energy, 34, 953–957.
- 6. Khattab, K., & Sulieman, I. (2009). Calculations of the thermal and fast neutron fluxes in the Syrian MNSR irradiation tubes using the MCNP-4C code. Appl. Radiat. Isot., 67, 535–538.
- 7. Balogun, G. I. (2003). Automating some analysis and design calculations of miniature neutron source reactors at CERT (1). Ann. Nucl. Energy, 30, 81–92.
- 8. Tayyab, M., Showket, P., & Masood, I. (2008). Neutronic analysis for core conversion (HEU-LEU) of Pakistan research reactor-2 (PARR-2). Ann. Nucl. Energy, 35, 1440–1446.
- 9. Hainoun, A., Hajhassan, H., & Ghazi, N. (2009). Determination of major kinetic parameters of the Syrian MNSR for different fuel loading using Monte Carlo technique. Ann. Nucl. Energy, 36, 1663–1667.