TY - GEN
T1 - Preliminary investigation of candidate materials for use in accident resistant fuel
AU - Harp, Jason M.
AU - Lessing, Paul A.
AU - Park, Blair H.
AU - Maupin, Jakeob
PY - 2013
Y1 - 2013
N2 - As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.
AB - As part of a Collaborative Research and Development Agreement (CRADA) with industry, Idaho National Laboratory (INL) is investigating several options for accident resistant uranium compounds including silicides, and nitrides for use in future light water reactor (LWR) fuels. This work is part of a larger effort to create accident tolerant fuel forms where changes to the fuel pellets, cladding, and cladding treatment are considered. The goal fuel form should have a resistance to water corrosion comparable to UO2, have an equal to or larger thermal conductivity than uranium dioxide, a melting temperature that allows the material to stay solid under power reactor conditions, and a uranium loading that maintains or improves current LWR power densities. During the course of this research, fuel fabricated at INL will be characterized, irradiated at the INL Advanced Test Reactor, and examined after irradiation at INL facilities to help inform industrial partners on candidate technologies.
UR - https://www.scopus.com/pages/publications/84902318103
M3 - Conference contribution
AN - SCOPUS:84902318103
SN - 9781629937212
T3 - LWR Fuel Performance Meeting, Top Fuel 2013
SP - 757
EP - 762
BT - LWR Fuel Performance Meeting, Top Fuel 2013
PB - American Nuclear Society
T2 - LWR Fuel Performance Meeting, Top Fuel 2013
Y2 - 15 September 2013 through 19 September 2013
ER -