Comparative Study of Fuel Materials for the Kijang Research Reactor. Annex II

The Korea Atomic Energy Research Institute (KAERI) has been developing a new research reactor, the Kijang Research Reactor (KJRR) [II–1]. The KJRR will mainly be used for isotope production, neutron transmutation doping (NTD) production and related research activities. The KJRR is a medium flux reactor of 15 MW using materials testing reactor (MTR) type fuel assemblies (FAs), which use uranium–molybdenum (U–Mo) with 7 wt% Mo (U–7 Mo) dispersion fuel, with a uranium density of 8.0gU/cm³, as a reference fuel. Its fuel has not yet been fully qualified, but the KJRR adopts high density fuel for higher fuel economy. A silicide uranium fuelled KJRR core was prepared in order to understand the U–7Mo core well and to obtain a fallback option. This report presents a nuclear comparative study on the differently fuelled cores.