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Irradiation testing of enhanced uranium oxide fuels
Insulander Bjö,rk, Klara,Kelly, Julian F.,Vitanza, Carlo,Drera, Saleem S.,Holcombe, Scott,Tverberg, Terje,Tuomisto, Harri,Wright, Jonathan,Sarsfield, Mark,Blench, Trevor,Yang, Jae Ho,Kim, Hyun-Gil Elsevier 2019 Annals of nuclear energy Vol.125 No.-
<P><B>Abstract</B></P> <P>Enhanced uranium oxide fuel types are being tested in the Halden Research Reactor in Norway with the aim is to assess the effect that these enhancements have on fuel performance. Fuel temperatures, rod pressures and dimensional changes are being monitored online and an extensive post-irradiation examination programme is planned. Preliminary data show that fuel centerline temperatures can be lowered by addition of ThO<SUB>2</SUB> to the fuel matrix, or by incorporating Cr or SiO<SUB>2</SUB>-TiO<SUB>2</SUB> as a network structure within the fuel. In parallel, two types of cladding coatings are tested in order to investigate their in-core properties. No abnormal behaviour has been noted during the first 100 days of irradiation.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Irradiation testing of uranium oxide fuel enhanced with Cr, SiO<SUB>2</SUB>/TiO<SUB>2</SUB> and ThO<SUB>2</SUB>. </LI> <LI> Irradiation testing of cladding coated with (Fe,Cr,Al) and (Cr,Al) alloys. </LI> <LI> All tested materials perform as expected, or better. </LI> <LI> Lowered fuel temperatures observed for fuel enhanced with Cr microcell structure. </LI> <LI> Unexpectedly low temperatures observed for SiO<SUB>2</SUB>/TiO<SUB>2</SUB> and 40% ThO<SUB>2</SUB> enhanced fuel. </LI> </UL> </P>