TY - GEN
T1 - Studies of MYRRHA using thorium fuel
AU - Barlow, Roger
AU - Burlison, James
AU - Edwards, Tristan
AU - Healy, Alisa
AU - Masterson, Alex
AU - Aït Abderrahim, Hamid
AU - Malambu Mbala, Edouard
AU - Van den Eynde, Gert
N1 - Score=10
PY - 2016/5/11
Y1 - 2016/5/11
N2 - The problem of long-lived radioactive waste has yet to find an acceptable solution, with political opposition to geological storage remaining strong. One possible solution which has often been discussed is to use ADSR systems for its incineration. The advantages of thorium as a fuel in this process are obvious, but few detailed numerical studies have been performed. We investigate the potential for using a thorium fuelled subcritical reactor for the incineration of long-lived minor actinide radioactive waste, based on the well-developed MYRRHA reactor design, operating in sub-critical mode. We examine the neutron fluxes and spectra in the reactor, particularly in the In-Pile Section (IPS) regions that would be appropriate for such transmutation, comparing the result from thorium fuel rods with those of the standard uranium/plutonium fuel. From this we present the burn-up rates that would be achieved, both initially and in the longer term as 233U is formed.
AB - The problem of long-lived radioactive waste has yet to find an acceptable solution, with political opposition to geological storage remaining strong. One possible solution which has often been discussed is to use ADSR systems for its incineration. The advantages of thorium as a fuel in this process are obvious, but few detailed numerical studies have been performed. We investigate the potential for using a thorium fuelled subcritical reactor for the incineration of long-lived minor actinide radioactive waste, based on the well-developed MYRRHA reactor design, operating in sub-critical mode. We examine the neutron fluxes and spectra in the reactor, particularly in the In-Pile Section (IPS) regions that would be appropriate for such transmutation, comparing the result from thorium fuel rods with those of the standard uranium/plutonium fuel. From this we present the burn-up rates that would be achieved, both initially and in the longer term as 233U is formed.
KW - MYRRHA
KW - Thorium
KW - Core design
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35765962
U2 - 10.1016/j.ijhydene.2016.02.141
DO - 10.1016/j.ijhydene.2016.02.141
M3 - In-proceedings paper
VL - 41
T3 - International Journal of Hydrogen Energy
SP - 7175
EP - 7180
BT - INTERNATIONAL JOURNAL OF HYDROGEN ENERGY
ER -