NEUTRONIC EVALUATION OF DUPIC CYCLE ¿ USE OF H2O AS COOLANT

Autores UPV
Año
CONGRESO NEUTRONIC EVALUATION OF DUPIC CYCLE ¿ USE OF H2O AS COOLANT

Abstract

The CANDU (CANada Deuterium Uranium) reactor uses natural uranium, and heavy water is used as both the coolant and moderator. Deuterium has a low probability of neutron absorption and this behavior allows natural uranium to be used as fuel. Nevertheless, recent studies confirm the potential of using reprocessed PWR (Pressurized Water Reactor) fuels in the CANDU fuel cycle. A important proposal is the ¿Direct Use of spent PWR fuel In CANDU¿ (DUPIC) cycle, where spent fuels from a PWR is packaged into a CANDU fuel bundle with only mechanical reprocessing (cut into pieces) but no chemical reprocessing. Two reprocessing techniques have been considered: AIROX (Atomics International Reduction Oxidation) and OREOX (Oxidation and REduction of OXide fuel). The fissile content of the spent fuels from PWR is about 1.5 wt%, which is higher than that of the fuels of CANDU reactor. Using the DUPIC cycle, the probability of fission increases; in this way, it could be possible to use H2O, which presents a higher absorption cross section than D2O. This work analyzes the use of DUPIC cycle in a CANDU-6 reactor with light water as coolant. Two reprocessed fuels have been considered: FRA (Fuel Reprocessed by AIROX technique) and FRO (Fuel Reprocessed by OREOX technique). The goal is to analyze the effective multiplication factor, void reactivity coefficient and neutron flux for the recharged reactor core with reprocessed fuel at BOL (Begin Of Life) and zero power condition. The MCNPX 2.6.0 code has been used to model the system.