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Corrigendum to “Thermodynamics of soluble fission products cesium and iodine in the Molten Salt Reactor” [Journal of Nuclear Materials Volume 501 (2018) pages 238-252]

Journal of nuclear materials, 2021-11, Vol.555, p.153156, Article 153156

2021

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The thermodynamic properties of gaseous UO2(OH)2

Journal of nuclear materials, 2017-12, Vol.496, p.163-165

2017

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High temperature heat capacity of (U, Am)O2±x

Journal of nuclear materials, 2017-10, Vol.494, p.95-102

2017

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Traceability Improvement of High Temperature Thermal Property Measurements of Materials for New Fission Reactors

IEEE transactions on nuclear science, 2014-08, Vol.61 (4), p.2112-2119

2014

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Thermodynamics of soluble fission products cesium and iodine in the Molten Salt Reactor

Journal of nuclear materials, 2018-04, Vol.501, p.238-252

2018

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Cesium and iodine release from fluoride-based molten salt reactor fuel

Physical chemistry chemical physics : PCCP, 2021-04, Vol.23 (15), p.9512-9523

2021

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Thermodynamic investigations of the NaI-CsI, KI-CsI, and NaF-CsI pseudo-binary systems

The Journal of chemical thermodynamics, 2024-06, Vol.193, p.107272, Article 107272

2024

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Electrochemical measurements of LiF-CaF2-ThF4 melt and activity coefficient of ThF4 in LiF-CaF2 eutectic melt

Electrochimica acta, 2021-06, Vol.380, p.138198, Article 138198

2021

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High temperature heat capacity of Nd2Zr2O7 and La2Zr2O7 pyrochlores

The Journal of chemical thermodynamics, 2005-10, Vol.37 (10), p.1098-1103

2005

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Thermodynamic assessment of the LiF–ThF4–PuF3–UF4 system

Journal of nuclear materials, 2015-07, Vol.462, p.43-53

2015

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Joint Raman spectroscopic and quantum chemical analysis of the vibrational features of Cs 2 RuO 4

Journal of Raman spectroscopy, 2015-07, Vol.46 (7), p.661-668

2015

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Experimental investigation and thermodynamic modelling of the ThF4-PuF3 phase diagram

Journal of nuclear materials, 2023-12, Vol.587, p.154682, Article 154682

2023

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Thermodynamic modelling of thoria-urania and thoria-plutonia fuels: Description of the Th-U-Pu-O quaternary system

Journal of nuclear materials, 2018-12, Vol.512, p.324-348

2018

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Coupled Computational Fluid Dynamics and Computational Thermodynamics Simulations for Chemically Reacting Flows with Phase Transformations: A Fluoride Volatility Process Example

Annals of nuclear energy, 2024-04, Vol.198, p.110327, Article 110327

2024

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The molten salt reactor (MSR) in generation IV: Overview and perspectives

Progress in nuclear energy (New series), 2014-11, Vol.77, p.308-319

2014

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Thermodynamic properties and phase diagrams of fluoride salts for nuclear applications

Journal of fluorine chemistry, 2009, Vol.130 (1), p.22-29

2009

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Thermodynamic behavior of CrF2 corrosion product in the molten LiF-ThF4 salt system

Calphad, 2024-09, Vol.86, p.102722, Article 102722

2024

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Thermodynamic investigations of the LiF-CsF and NaF-CsF pseudo-binary systems

Journal of nuclear materials, 2022-09, Vol.568, p.153901, Article 153901

2022

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Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor

Journal of nuclear materials, 2019-12, Vol.527, p.151780, Article 151780

2019

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Corrigendum of “Thermodynamic modelling of thoria-urania and thoria-plutonia fuels: Description of the Th-U-Pu-O quaternary system”

Journal of nuclear materials, 2024-10, Vol.599, p.155250, Article 155250

2024

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The high-temperature heat capacity of the (Th,U)O2 and (U,Pu)O2 solid solutions

Journal of nuclear materials, 2017-02, Vol.484 (C), p.1-6

2017

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Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system

Journal of nuclear materials, 2018-09, Vol.508, p.319-328

2018

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Thermodynamic assessment of the LiF―NaF―ThF4―UF4 system

Journal of nuclear materials, 2010-10, Vol.405 (2), p.186-198

2010

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Excess Heat Capacity in Liquid Binary Alkali-Fluoride Mixtures

Inorganic chemistry, 2013-03, Vol.52 (5), p.2404-2411

2013

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Low- and high-temperature heat capacity of metallic technetium

The Journal of chemical thermodynamics, 2024-02, Vol.189, p.107200, Article 107200

2024

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Corrigendum to “Thermodynamics of soluble fission products cesium and iodine in the Molten Salt Reactor” [Journal of Nuclear Materials Volume 501 (2018) pages 238-252]

The thermodynamic properties of gaseous UO2(OH)2

High temperature heat capacity of (U, Am)O2±x

Traceability Improvement of High Temperature Thermal Property Measurements of Materials for New Fission Reactors

Thermodynamics of soluble fission products cesium and iodine in the Molten Salt Reactor

Cesium and iodine release from fluoride-based molten salt reactor fuel

Thermodynamic investigations of the NaI-CsI, KI-CsI, and NaF-CsI pseudo-binary systems

Electrochemical measurements of LiF-CaF2-ThF4 melt and activity coefficient of ThF4 in LiF-CaF2 eutectic melt

High temperature heat capacity of Nd2Zr2O7 and La2Zr2O7 pyrochlores

Thermodynamic assessment of the LiF–ThF4–PuF3–UF4 system

Joint Raman spectroscopic and quantum chemical analysis of the vibrational features of Cs 2 RuO 4

Experimental investigation and thermodynamic modelling of the ThF4-PuF3 phase diagram

Thermodynamic modelling of thoria-urania and thoria-plutonia fuels: Description of the Th-U-Pu-O quaternary system

Coupled Computational Fluid Dynamics and Computational Thermodynamics Simulations for Chemically Reacting Flows with Phase Transformations: A Fluoride Volatility Process Example

The molten salt reactor (MSR) in generation IV: Overview and perspectives

Thermodynamic properties and phase diagrams of fluoride salts for nuclear applications

Thermodynamic behavior of CrF2 corrosion product in the molten LiF-ThF4 salt system

Thermodynamic investigations of the LiF-CsF and NaF-CsF pseudo-binary systems

Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor

Corrigendum of “Thermodynamic modelling of thoria-urania and thoria-plutonia fuels: Description of the Th-U-Pu-O quaternary system”

The high-temperature heat capacity of the (Th,U)O2 and (U,Pu)O2 solid solutions

Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system

Thermodynamic assessment of the LiF―NaF―ThF4―UF4 system

Excess Heat Capacity in Liquid Binary Alkali-Fluoride Mixtures

Low- and high-temperature heat capacity of metallic technetium

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