Neutronic Analysis of (ThO_2-~(Enriched)UO_2) Replacement with ~(nat)UO_2 Fuel in a Typical Heavy Water Research Reactor

摘要

Theoretical and experimental investigations, which are exclusively carried out, reveal that thorium-based fuel could potentially be a proper alternative in nuclear fuel cycle technology. In this study, the neutronic impacts of such cycle as a consequence of_(nat)UO~(2)fuel substitution with an enriched uranium/thorium oxide fuel in a heavy water research reactor is presented. The obtained computational data shows that the thorium-based fuel has a less negative temperature coefficient comparing to UO~(2)fuel. Meantime, the thorium-based fuel loading in a typical core configuration does not drastically reduce the β as in case of UO~(2)fuel. Rather higher conversion factor and less transuranic production in the thorium-based fuel cycle make it favorable either to achieve higher cycle length or less dangerous and costly waste disposal.