Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets

Atomic Energy Organization of Iran, 2009. Safety Analysis Report for Tehran Research Reactor (TRR). vol. 1, chapter 5. ANSYS, 2014. ANSYS-fluent User's Guide. Release 15.0. Domingos, D.B., Silva, A.T., Silva, J.E.R., João, T.G., 2011. Neutronic analysis for production of fission molybdenum-99 at IEA-R1 and RMB research reactors. INIS-BE--11N0031, Belgium. Abbate, P., Mazufri, C., 1998. CAUDVAP MODE 3.60: A computer program for flow distribution and pressure drop calculation in a MTR type core. INVAP Co. Abbate, 2003 Cho, 1999, Nuclear design methodology of fission moly target for research reactor, J. Korean Nucl. Soc., 31, 365 Croff, 1980 Denise, 2008 Jo, 2014, Neutronic and thermal-hydraulic analyses of irradiated fuel plates for molybdenum-99 production, Ann. Nucl. Energy, 71, 467, 10.1016/j.anucene.2014.04.017 Mohammad, 2009, Fission moly production at PARR-1 using LEU plate type target, Nucl. Eng. Des. Vol., 239, 521, 10.1016/j.nucengdes.2008.11.008 Mushtaq, 2008, Neutronic and thermal-hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1, Ann. Nucl. Energy, 35, 345, 10.1016/j.anucene.2007.06.006 Zaker, 1995, 17