1. Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1;Ahmad;Ann. Nucl. Energy,2008
2. A User's Manual for the ORIGEN Computer Code;Croff,1980
3. Deen, J.R., Woodruff, W.L., Costescu, C.I., 1995. WIMS/D4 User Manual REV.0 ANL/RERTR/TM-23.
4. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear Reactor Core Analyses Code CITATION, ORNL – TM – 2496, Rev. 2.
5. FSAR, 1999. Final Safety Analysis Report of PARR-1.