Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

Development of fuel performance analysis code, BISON for MOX, named Okami: Analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring

(2021) Takayuki Ozawa et al.   JOURNAL OF NUCLEAR MATERIALS

A new heat capacity law for UO2, PuO2 and (U,Pu)O2 derived from molecular dynamics simulations and useable in fuel performance codes

(2021) Didier Bathellier et al.   JOURNAL OF NUCLEAR MATERIALS

SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

(2020) D. Pizzocri et al.   JOURNAL OF NUCLEAR MATERIALS

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

Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

(2020) T. Barani et al.   JOURNAL OF NUCLEAR MATERIALS

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

(2020) A. Magni et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal diffusivity and conductivity of thorium- uranium mixed oxides

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

The Effects of Plutonium Content and Self-Irradiation on Thermal Conductivity of Mixed Oxide Fuel

(2018) Yoshihisa Ikusawa et al.   NUCLEAR TECHNOLOGY

Outcomes of the PELGRIMM project on Am-bearing fuel in pelletized and spherepac forms

(2018) A. Gallais-During et al.   JOURNAL OF NUCLEAR MATERIALS

The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO 2−x for americium breading blanket concept

(2017) E. D'Agata et al.   NUCLEAR ENGINEERING AND DESIGN

Molecular dynamics study of thermal conductivities of (U 0.7−x Pu 0.3 Am x )O 2

(2016) Weiwei Li 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

Modelling the thermal conductivity of (U x Th 1−x )O 2 and (U x Pu 1−x )O 2

(2015) M.W.D. Cooper et al.   JOURNAL OF NUCLEAR MATERIALS

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

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

Effect of burn-up on the thermal conductivity of uranium–gadolinium dioxide up to 100 GWd/tHM

(2014) D. Staicu 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

MYRRHA – A multi-purpose fast spectrum research reactor

(2012) Hamid Aït Abderrahim et al.   ENERGY CONVERSION AND MANAGEMENT

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

(2012) Masato KATO et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

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 diffusivity and conductivity of thorium–plutonium mixed oxides

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

Preparation and characterization of the simulated burnup americium-containing uranium–plutonium mixed oxide fuel

(2011) Kosuke Tanaka et al.   JOURNAL OF NUCLEAR MATERIALS

Short-term irradiation behavior of low-density americium-doped uranium–plutonium mixed oxide fuels irradiated in a fast reactor

(2010) K. Maeda et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivity of (U,Pu,Np)O2 solid solutions

(2009) Kyoichi Morimoto et al.   JOURNAL OF NUCLEAR MATERIALS

Radial redistribution of actinides in irradiated FR-MOX fuels

(2009) Koji Maeda et al.   JOURNAL OF NUCLEAR MATERIALS

Nuclear fuels – Present and future

(2009) D. Olander   JOURNAL OF NUCLEAR MATERIALS

Behavior of Si impurity in Np–Am–MOX fuel irradiated in the experimental fast reactor Joyo

(2008) Koji Maeda et al.   JOURNAL OF NUCLEAR MATERIALS

Short-term irradiation behavior of minor actinide doped uranium plutonium mixed oxide fuels irradiated in an experimental fast reactor

(2008) K. Maeda et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal conductivities of (U, Pu, Am)O2 solid solutions

(2007) Kyoichi Morimoto et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Solidus and liquidus of plutonium and uranium mixed oxide

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

Thermal conductivities of hypostoichiometric (U, Pu, Am)O2−x oxide

(2007) Kyoichi Morimoto et al.   JOURNAL OF NUCLEAR MATERIALS

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