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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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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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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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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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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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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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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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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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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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Coupled computational fluid dynamics and computational thermodynamics simulations for fission product retention and release: A molten salt fast reactor application

Progress in nuclear energy (New series), 2024-12, Vol.177, p.105450, Article 105450

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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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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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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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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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

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

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

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

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

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

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

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

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

Coupled computational fluid dynamics and computational thermodynamics simulations for fission product retention and release: A molten salt fast reactor application

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

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

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

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

Low- and high-temperature heat capacity of metallic technetium

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