TAF-ID: An international thermodynamic database for nuclear fuels applications

Simulation of the chemical state of high burnup (U,Pu)O2 fuel in fast reactors based on thermodynamic calculations

(2020) Karl Samuelsson et al.   JOURNAL OF NUCLEAR MATERIALS

Modeling and simulation of oxygen transport in high burnup LWR fuel

(2020) Srdjan Simunovic et al.   JOURNAL OF NUCLEAR MATERIALS

Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques

(2019) Riley J. Parrish et al.   JOURNAL OF NUCLEAR MATERIALS

U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences

(2019) Jason M. Harp et al.   JOURNAL OF NUCLEAR MATERIALS

Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

(2019) Laurent Brissonneau et al.   JOURNAL OF NUCLEAR MATERIALS

A review of microstructural features in fast reactor mixed oxide fuels

(2018) Riley Parrish et al.   JOURNAL OF NUCLEAR MATERIALS

Contribution to the thermodynamic description of the corium – The U-Zr-O system

(2018) A. Quaini et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic investigations of the uranium-molybdenum-oxygen system by a coupling of density functional theory and CALPHAD methodologies

(2018) E.C. Corcoran et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

TEM characterization of irradiated U-7Mo/Mg dispersion fuel

(2017) J. Gan et al.   JOURNAL OF NUCLEAR MATERIALS

Oxygen diffusion model of the mixed (U,Pu)O 2 ± x : Assessment and application

(2017) Emily Moore et al.   JOURNAL OF NUCLEAR MATERIALS

Structure and thermal properties of as-fabricated U-7Mo/Mg and U-10Mo/Mg low-enriched uranium research reactor fuels

(2017) Mykola Kulakov et al.   JOURNAL OF NUCLEAR MATERIALS

Experimental contribution to the corium thermodynamic modelling – The U–Zr–Al–Ca–Si–O system

(2016) A. Quaini et al.   ANNALS OF NUCLEAR ENERGY

Thermodynamic assessment of the PdRhRu system using calphad and first-principles methods

(2016) S. Gossé et al.   JOURNAL OF NUCLEAR MATERIALS

Measurement of the oxygen partial pressure and thermodynamic modeling of the U–Nd–O system

(2016) Seung Min Lee et al.   JOURNAL OF NUCLEAR MATERIALS

Experimental oxygen potentials for U 1−y Pr y O 2±x and thermodynamic assessment of the U-Pr-O system

(2016) J.W. McMurray et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic assessment of the Cs–Te binary system

(2015) T.-N. Pham Thi et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

Thermodynamic assessment of the cesium–oxygen system by coupling density functional theory and CALPHAD approaches

(2015) C. Guéneau et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

Growth behavior of intermetallic compounds during reactive diffusion between aluminum alloy 1060 and magnesium at 573–673 K

(2015) Lin Xiao et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic assessment of the U–La–O system

(2015) J.W. McMurray et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic assessment of the U–Y–O system

(2015) R.G. Brese et al.   JOURNAL OF NUCLEAR MATERIALS

On the interpretation of chemical potentials computed from equilibrium thermodynamic codes

(2015) M.H.A. Piro et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic assessment of the oxygen rich U–Ce–O system

(2015) J.W. McMurray et al.   JOURNAL OF NUCLEAR MATERIALS

3D thermo-chemical–mechanical simulation of power ramps with ALCYONE fuel code

(2014) B. Baurens et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic reassessment of U–Gd–O system

(2014) J.W. McMurray et al.   JOURNAL OF NUCLEAR MATERIALS

Conjugate heat transfer simulations of advanced research reactor fuel

(2014) M.H.A. Piro et al.   NUCLEAR ENGINEERING AND DESIGN

Thermochemical modeling of the U1−yGdyO2±x phase

(2013) J.W. McMurray et al.   JOURNAL OF NUCLEAR MATERIALS

Diffusion model of the non-stoichiometric uranium dioxide

(2013) Emily Moore et al.   JOURNAL OF SOLID STATE CHEMISTRY

The thermochemistry library Thermochimica

(2012) M.H.A. Piro et al.   COMPUTATIONAL MATERIALS SCIENCE

Multidimensional multiphysics simulation of nuclear fuel behavior

(2012) R.L. Williamson et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic modeling of the (U,La)O2±x solid solution phase

(2012) Dongwon Shin et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic assessment of the palladium–tellurium (Pd–Te) system

(2011) S. Gossé et al.   INTERMETALLICS

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

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

A thermodynamic study of the Pu–Am–O system

(2011) P. Gotcu-Freis et al.   JOURNAL OF NUCLEAR MATERIALS

Calphad thermodynamic description of some binary systems involving U

(2011) A. Berche et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

(2011) Christine Guéneau et al.   JOURNAL OF NUCLEAR MATERIALS

PERFORMANCE EVALUATION OF U-Mo/Al DISPERSION FUEL BY CONSIDERING A FUEL-MATRIX INTERACTION

(2011) Ho-Jin Ryu et al.   Nuclear Engineering and Technology

Unified derivation of phase-field models for alloy solidification from a grand-potential functional

(2011) Mathis Plapp   PHYSICAL REVIEW E

Thermodynamic study of the uranium–vanadium system

(2010) A. Berche et al.   JOURNAL OF CHEMICAL THERMODYNAMICS

Thermodynamic study of the U–Si system

(2009) A. Berche et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic modelling of the plutonium–oxygen system

(2008) Christine Guéneau et al.   JOURNAL OF NUCLEAR MATERIALS

Corium phase equilibria based on MASCA, METCOR and CORPHAD results

(2008) S.V. Bechta et al.   NUCLEAR ENGINEERING AND DESIGN

Thermodynamic modeling of the Al–U and Co–U systems

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