Neutron-Physical and Radiation Characteristics of Different Low Enrichment Fuels (Thorium and Uranium) in a Proposed JRTR Research Reactor

Abstract

The Jordan Research and Training Reactor (JRTR) is a 5-MWth, open-pool type, light-water moderated and cooled reactor with a heavy-water reflector system. The core consists of standard Material Testing Reactor (MTR), the plate type of fuel assemblies with low enriched fuel of 19.75% U-235 enrichment. One of the most important purposes of JRTR is producing several radioisotopes e.g. (⁹⁹Mo/^99mTc, ¹³¹I and ¹⁹²Ir isotopes) by using the neutron activation technology. A new computational model has been developed for different low enrichment fuels (Thorium and Uranium) in the JRTR by using the Serpent Monte Carlo code. The purpose of this paper is to validate Th-U233 fuel by comparison of the calculation results of important neutronics parameters, like k_eff, flux distribution, kinetics parameters, power peaking factors, heat decay and activity of spent fuel.