Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

Using molecular dynamics to predict the solidus and liquidus of mixed oxides (Th,U)O2, (Th,Pu)O2 and (Pu,U)O2

(2020) C.O.T. Galvin et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal transport study in actinide oxides with point defects

(2019) Alex Resnick et al.   Nuclear Engineering and Technology

Model updates and performance evaluations on fuel performance code FEMAXI-8 for light water reactor fuel analysis

(2019) Yutaka Udagawa et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Thermal diffusivity and conductivity of thorium- uranium mixed oxides

(2018) M. Saoudi et al.   JOURNAL OF NUCLEAR MATERIALS

GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors

(2018) Marc Lainet et al.   JOURNAL OF NUCLEAR MATERIALS

Melting behavior of mixed U–Pu oxides under oxidizing conditions

(2016) Michal Strach et al.   NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS

Linear thermal expansion, thermal diffusivity and melting temperature of Am-MOX and Np-MOX

(2015) D. Prieur et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Melting temperature of MOX fuel for FBR applications: TRANSURANUS modelling and experimental findings

(2015) R. Calabrese et al.   NUCLEAR ENGINEERING AND DESIGN

Recent advances in the study of the UO2–PuO2 phase diagram at high temperatures

(2014) R. Böhler et al.   JOURNAL OF NUCLEAR MATERIALS

Generation IV nuclear reactors: Current status and future prospects

(2013) Giorgio Locatelli et al.   ENERGY POLICY

Thermal conductivity of heterogeneous LWR MOX fuels

(2013) D. Staicu et al.   JOURNAL OF NUCLEAR MATERIALS

Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel

(2013) Melissa Teague et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivity evaluation of high burnup mixed-oxide (MOX) fuel pellet

(2011) Masaki Amaya et al.   JOURNAL OF NUCLEAR MATERIALS

Burnup dependence of melting temperature of FBR mixed oxide fuels irradiated to high burnup

(2011) Takashi Hirosawa et al.   JOURNAL OF NUCLEAR MATERIALS

On the melting behaviour of uranium/plutonium mixed dioxides with high-Pu content: A laser heating study

(2011) F. De Bruycker et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivity of homogeneous and heterogeneous MOX fuel with up to 44MWd/kgHM burn-up

(2011) D. Staicu et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal diffusivity and conductivity of thorium–plutonium mixed oxides

(2011) C. Cozzo et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal diffusivity of homogeneous SBR MOX fuel with a burn-up of 35MWd/kgHM

(2010) C. Cozzo et al.   JOURNAL OF NUCLEAR MATERIALS

Reassessing the melting temperature of PuO2

(2010) Franck De Bruycker et al.   Materials Today

Nuclear fuels – Present and future

(2009) D. Olander   JOURNAL OF NUCLEAR MATERIALS

Solidus and liquidus of plutonium and uranium mixed oxide

(2007) Masato Kato et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Detailed characterisations of high burn-up structures in oxide fuels

(2007) J. Noirot et al.   JOURNAL OF NUCLEAR MATERIALS

Solidus and liquidus temperatures in the UO2–PuO2 system

(2007) M. Kato et al.   JOURNAL OF NUCLEAR MATERIALS