Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector.
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| Title: | Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector. |
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| Authors: | Barker, Adam J.1 (AUTHOR) adam.barker-3@manchester.ac.uk, Gilbert, Mark R.2 (AUTHOR), Edmondson, Philip D.1 (AUTHOR) |
| Source: | Nuclear Fusion. Aug2025, Vol. 65 Issue 8, p1-12. 12p. |
| Subjects: | Tritium, Fusion reactor blankets, Neutron flux, Fusion reactors, Neutron reflectivity, Fused salts |
| Abstract: | Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant. Tritium is a rare resource, currently produced only in a limited number of fission reactors and other low-output facilities. Due to the lack of experimental data in this area, neutronics calculations will guide the design of the first-generation fusion blankets tasked with tritium fuel production as without maximised breeding potential, reactor startup times may need to be postponed due to a low global inventory. This paper describes an optimisation workflow that segments a DEMO-style blanket to allow flexibility in material allocation, along with the necessary validation steps for repeatable results. The developed blanket is tested within the neutronics code OpenMC to evaluate the performance of a hybrid liquid metal–molten salt breeder. FLiBe is found to be an efficient neutron reflector, showing performance increases of 7%, resulting in an overall tritium breeding ratio (TBR) of 1.11, even with a natural abundance of 7.5 % lithium-6. Analysis of the neutron spectral profile indicates a shift towards thermal neutrons when reflected from FLiBe placed at the rear of the design. The use of molten salt as a reflector is novel as a result of its ability to breed tritium and provide a secondary increase in TBR through the reflection of neutrons. A dual system would require more complex engineering, but may offer a solution for compact reactors and/or systems with low lithium enrichment. [ABSTRACT FROM AUTHOR] |
| Copyright of Nuclear Fusion is the property of IOP Publishing 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: 187906148 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Barker%2C+Adam+J%2E%22">Barker, Adam J.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> adam.barker-3@manchester.ac.uk</i><br /><searchLink fieldCode="AR" term="%22Gilbert%2C+Mark+R%2E%22">Gilbert, Mark R.</searchLink><relatesTo>2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Edmondson%2C+Philip+D%2E%22">Edmondson, Philip D.</searchLink><relatesTo>1</relatesTo> (AUTHOR) – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Nuclear+Fusion%22">Nuclear Fusion</searchLink>. Aug2025, Vol. 65 Issue 8, p1-12. 12p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Tritium%22">Tritium</searchLink><br /><searchLink fieldCode="DE" term="%22Fusion+reactor+blankets%22">Fusion reactor blankets</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+flux%22">Neutron flux</searchLink><br /><searchLink fieldCode="DE" term="%22Fusion+reactors%22">Fusion reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+reflectivity%22">Neutron reflectivity</searchLink><br /><searchLink fieldCode="DE" term="%22Fused+salts%22">Fused salts</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant. Tritium is a rare resource, currently produced only in a limited number of fission reactors and other low-output facilities. Due to the lack of experimental data in this area, neutronics calculations will guide the design of the first-generation fusion blankets tasked with tritium fuel production as without maximised breeding potential, reactor startup times may need to be postponed due to a low global inventory. This paper describes an optimisation workflow that segments a DEMO-style blanket to allow flexibility in material allocation, along with the necessary validation steps for repeatable results. The developed blanket is tested within the neutronics code OpenMC to evaluate the performance of a hybrid liquid metal–molten salt breeder. FLiBe is found to be an efficient neutron reflector, showing performance increases of 7%, resulting in an overall tritium breeding ratio (TBR) of 1.11, even with a natural abundance of 7.5 % lithium-6. Analysis of the neutron spectral profile indicates a shift towards thermal neutrons when reflected from FLiBe placed at the rear of the design. The use of molten salt as a reflector is novel as a result of its ability to breed tritium and provide a secondary increase in TBR through the reflection of neutrons. A dual system would require more complex engineering, but may offer a solution for compact reactors and/or systems with low lithium enrichment. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Nuclear Fusion is the property of IOP Publishing 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: 10.1088/1741-4326/adecb2 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 12 StartPage: 1 Subjects: – SubjectFull: Tritium Type: general – SubjectFull: Fusion reactor blankets Type: general – SubjectFull: Neutron flux Type: general – SubjectFull: Fusion reactors Type: general – SubjectFull: Neutron reflectivity Type: general – SubjectFull: Fused salts Type: general Titles: – TitleFull: Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Barker, Adam J. – PersonEntity: Name: NameFull: Gilbert, Mark R. – PersonEntity: Name: NameFull: Edmondson, Philip D. IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 08 Text: Aug2025 Type: published Y: 2025 Identifiers: – Type: issn-print Value: 00295515 Numbering: – Type: volume Value: 65 – Type: issue Value: 8 Titles: – TitleFull: Nuclear Fusion Type: main |
| ResultId | 1 |
