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

Guéneau, C.; Dupin, N.; Kjellqvist, Lina; Geiger, E.; Kurata, Masaki; Gossé, Stéphane; Corcoran, E. C.; Quaini, A.; Hania, P.R.; Smith, Anna; Piro, M.H.A.; Besmann, Theodore M.; Turchi, P. E. A.; Dumas, Jean-Christophe; Welland, M.J.; Ogata, Takanari; Lee, B.O.; Kennedy, J. R.; Adkins, Cynthia A.; Bankhead, Mark; Costa, Davide

doi:10.1016/j.calphad.2020.102212

Cited by 70 publications

(29 citation statements)

References 70 publications

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“…Introïni et al further advanced the capabilities within AL-CYONE by coupling it with the open-source thermochemistry software OPENCALPHAD [6] to improve the handling of thermochemistry [62]. The primary motivation of this work was to leverage the much more complete Thermodynamics for Advanced Fuels-International Database (TAF-ID) database [63]. The TAF-ID is a sophisticated thermodynamic database, primarily aimed at UO 2 fuel, which has been coordinated by the Organization for Economic Co-operative Development Nuclear Energy Agency (OECD-NEA).…”

Section: Alcyonementioning

confidence: 99%

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Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Piro

2021

Thermo

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A number of codes are used to predict various aspects of nuclear fuel performance and safety, ranging from conventional fuel performance codes to simulate normal operating conditions to integral engineering codes to simulate severe accident behaviour. There has been a number of reportings in the open literature of nuclear fuel codes being informed by thermodynamic calculations, ranging from the use of simple thermodynamic correlations to direct coupling of equilibrium thermodynamic software. Progress in expanding predictive capabilities have been reported, which also includes advances in thermodynamic database development to better capture irradiated fuel. However, this progress has been accompanied by several challenges, including effective coupling of different types of physical phenomena in a practical manner and doing so with a reasonable increase in computational expense. This review paper will summarize previous experiences reported in the open literature in coupling thermodynamic calculations with nuclear fuel codes and applications, identify current challenges and limitations, and offer some perspectives for the community to consider moving forward.

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Section: Alcyonementioning

confidence: 99%

“…The TAF-ID has involved six NEA member states: Canada, European Commission, France, Japan, The Netherlands, Republic of Korea, and the United States. Version 11 of the database, which was used in this analysis, contained 210 assessed binary systems and 76 assessed ternary systems [63].…”

Section: Alcyonementioning

confidence: 99%

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Piro

2021

Thermo

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“…During an accident sequence, compositions as well as temperatures of the molte pool can vary. The CALPHAD databases as NUCLEA [14] or TAF-ID [16], which mode the corium chemistry in the entire composition region from metal to oxide, are used toda in the severe accident codes to predict the phases as function of temperature and compo sition. Regarding more specifically the thermochemistry of the U-O-Zr-Fe system in r ducing atmosphere conditions, the state of knowledge can be summarized as follows:…”

Section: High Temperature Regime (Above 2200 • C)mentioning

confidence: 99%

“…Even if th disagreement is not fully understood at this stage, different assumptions can be in voked to explain it, as a possible redistribution of some mobile species between th phases in case of insufficiently quick quenching or accuracy of the oxygen compos During an accident sequence, compositions as well as temperatures of the molten pool can vary. The CALPHAD databases as NUCLEA [14] or TAF-ID [16], which models the corium chemistry in the entire composition region from metal to oxide, are used today in the severe accident codes to predict the phases as function of temperature and composition. Regarding more specifically the thermochemistry of the U-O-Zr-Fe system in reducing atmosphere conditions, the state of knowledge can be summarized as follows:…”

Section: High Temperature Regime (Above 2200 • C)mentioning

confidence: 99%

“…Thermo 2021, 1 180 Programmes [8,9], the SARNET Networks of Excellence [10,11] and the Organisation for Economic Cooperation and Development (OECD) Programmes [12,13], severe accident experts have been interested in the production and the assessment of thermodynamic data for a number of compounds of reactor materials and fission products and complex phases mixing a large number of chemical elements. Using the CALPHAD method, thermodynamic databases for collecting all this knowledge in a consistent way have been developed [14][15][16]. Thanks to previously mentioned international programmes, in particular to the European Commission EURATOM Programmes, the European tool NUCLEA [14], has been developed for in-and ex-vessel corium applications, and intensively and continuously validated at IRSN [10,11], until now, with the technical support of the SIMAP Laboratory (Grenoble, France) and the contributions from EDF and CEA.…”

Section: Introductionmentioning

confidence: 99%

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Corium Experimental Thermodynamics: A Review and Some Perspectives

Barrachin

2021

Thermo

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More than 30 years ago a specialist meeting was held at Joint Research Center Ispra (Italy) from 15 to 17 January 1990 to review the current understanding of chemistry during severe accidents in light water reactors (LWR). Let us consider that, at the end of the 1980s, thermodynamics introduced in the severe accident codes was really poor. Only some equilibrium constants for a few simple reactions between stoichiometric compounds were used as well as some simple correlations giving estimates of solidus and liquidus temperatures. In the same time, the CALPHAD method was developed and was full of promise to approximate the thermodynamic properties of a complex thermochemical system by the way of a critical assessment of experimental data, a definition of a simple physical model and an optimisation procedure to define the values of the model parameters. It was evident that a nuclear thermodynamic database had to be developed with that new technique to obtain quite rapidly prominent progress in the knowledge of thermochemistry in the severe accident research area. Discussions focused on the important chemical phenomena that could occur across the wide range of conditions of a damaged nuclear plant. The most pressing need for improved chemical models is identified with condensed phase mixtures to model the corium progression. This paper reviews more than 30 years of experimental data production in the field of corium thermodynamics. This work has been conducted through multiple international programs (EURATOM, ISTC, OECD) as well as through more specific studies conducted at the national scale. This research has been capitalised in specific databases such as NUCLEA and TAF-ID, databases developed at IRSN and at CEA, respectively, and are now used in degradation models of the severe accident simulation codes. This research is presented in this paper. In the conclusion, we outline the research perspectives that need to be considered in order to address today’s and tomorrow’s issues.

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Application Research on Preparatory Heat Treatment Process of Marine Large-Size Gears

Rong,

2024

Lecture Notes on Data Engineering and Communications Technologies

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

Cited by 70 publications

References 70 publications

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Corium Experimental Thermodynamics: A Review and Some Perspectives

Application Research on Preparatory Heat Treatment Process of Marine Large-Size Gears

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