Thermodynamic assessment of the LiF–NaF–BeF2–ThF4–UF4 system.
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| Title: | Thermodynamic assessment of the LiF–NaF–BeF |
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| Authors: | Capelli, E.1, Beneš, O.1 ondrej.benes@ec.europa.eu, Konings, R.J.M.1 |
| Source: | Journal of Nuclear Materials. Jun2014, Vol. 449 Issue 1-3, p111-121. 11p. |
| Subjects: | Thermodynamics, Lithium compounds, Neutron capture, Melting points, Databases, Uranium alloys |
| Abstract: | Abstract: The present study describes the full thermodynamic assessment of the LiF–NaF–BeF2–ThF4–UF4 system which is one of the key systems considered for a molten salt reactor fuel. The work is an extension of the previously assessed LiF–NaF–ThF4–UF4 system with addition of BeF2 which is characterized by very low neutron capture cross section and a relatively low melting point. To extend the database the binary BeF2–ThF4 and BeF2–UF4 systems were optimized and the novel data were used for the thermodynamic assessment of BeF2 containing ternary systems for which experimental data exist in the literature. The obtained database is used to optimize the molten salt reactor fuel composition and to assess its properties with the emphasis on the melting behaviour. [Copyright &y& Elsevier] |
| Copyright of Journal of Nuclear Materials is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
| Database: | Engineering Source |
| FullText | Text: Availability: 0 |
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| Header | DbId: egs DbLabel: Engineering Source An: 96022355 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Thermodynamic assessment of the LiF–NaF–BeF<subscript>2</subscript>–ThF<subscript>4</subscript>–UF<subscript>4</subscript> system. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Capelli%2C+E%2E%22">Capelli, E.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Beneš%2C+O%2E%22">Beneš, O.</searchLink><relatesTo>1</relatesTo><i> ondrej.benes@ec.europa.eu</i><br /><searchLink fieldCode="AR" term="%22Konings%2C+R%2EJ%2EM%2E%22">Konings, R.J.M.</searchLink><relatesTo>1</relatesTo> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Journal+of+Nuclear+Materials%22">Journal of Nuclear Materials</searchLink>. Jun2014, Vol. 449 Issue 1-3, p111-121. 11p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Thermodynamics%22">Thermodynamics</searchLink><br /><searchLink fieldCode="DE" term="%22Lithium+compounds%22">Lithium compounds</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+capture%22">Neutron capture</searchLink><br /><searchLink fieldCode="DE" term="%22Melting+points%22">Melting points</searchLink><br /><searchLink fieldCode="DE" term="%22Databases%22">Databases</searchLink><br /><searchLink fieldCode="DE" term="%22Uranium+alloys%22">Uranium alloys</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: Abstract: The present study describes the full thermodynamic assessment of the LiF–NaF–BeF2–ThF4–UF4 system which is one of the key systems considered for a molten salt reactor fuel. The work is an extension of the previously assessed LiF–NaF–ThF4–UF4 system with addition of BeF2 which is characterized by very low neutron capture cross section and a relatively low melting point. To extend the database the binary BeF2–ThF4 and BeF2–UF4 systems were optimized and the novel data were used for the thermodynamic assessment of BeF2 containing ternary systems for which experimental data exist in the literature. The obtained database is used to optimize the molten salt reactor fuel composition and to assess its properties with the emphasis on the melting behaviour. [Copyright &y& Elsevier] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Journal of Nuclear Materials is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1016/j.jnucmat.2014.03.009 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 11 StartPage: 111 Subjects: – SubjectFull: Thermodynamics Type: general – SubjectFull: Lithium compounds Type: general – SubjectFull: Neutron capture Type: general – SubjectFull: Melting points Type: general – SubjectFull: Databases Type: general – SubjectFull: Uranium alloys Type: general Titles: – TitleFull: Thermodynamic assessment of the LiF–NaF–BeF2–ThF4–UF4 system. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Capelli, E. – PersonEntity: Name: NameFull: Beneš, O. – PersonEntity: Name: NameFull: Konings, R.J.M. IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 06 Text: Jun2014 Type: published Y: 2014 Identifiers: – Type: issn-print Value: 00223115 Numbering: – Type: volume Value: 449 – Type: issue Value: 1-3 Titles: – TitleFull: Journal of Nuclear Materials Type: main |
| ResultId | 1 |
