A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components.
Saved in:
| Title: | A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components. |
|---|---|
| Authors: | Messner, Mark C.1, Guosheng Ye1, Sham, T.-L.2 tingleung.sham@inl.gov |
| Source: | Nuclear Technology. 2023 Supplement, Vol. 209, pS60-S72. 13p. |
| Abstract: | High-temperature microreactors can play a role in developing reliable, portable energy sources for off-grid remote locations, microgrid concepts, and industrial process heat. Portability and passive safety criteria tend to skew microreactor structural component designs toward complex geometries, high thermal stresses, and design bases with large numbers of startup/shutdown cycles. Current design rules, as typified by Section III of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, are less than optimal for these conditions, particularly for preliminary component designs where developers need to rapidly consider a large number of potential component configurations. This paper presents a design method targeted toward rapid, efficient evaluation of preliminary component designs using modern finite element analysis. The new method retains key connections with the ASME Code rules and design data while streamlining the design approach. This paper presents the design method, several verification examples illustrating the similarities and differences between the new method and the current ASME rules, and the application of the new approach to the evaluation of a test article mimicking key features of a heat pipe-cooled microreactor. [ABSTRACT FROM AUTHOR] |
| Copyright of Nuclear Technology is the property of Taylor & Francis Ltd 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 |
|---|---|
| Header | DbId: egs DbLabel: Engineering Source An: 161273869 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
| IllustrationInfo | |
| Items | – Name: Title Label: Title Group: Ti Data: A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Messner%2C+Mark+C%2E%22">Messner, Mark C.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Guosheng+Ye%22">Guosheng Ye</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Sham%2C+T%2E-L%2E%22">Sham, T.-L.</searchLink><relatesTo>2</relatesTo><i> tingleung.sham@inl.gov</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Nuclear+Technology%22">Nuclear Technology</searchLink>. 2023 Supplement, Vol. 209, pS60-S72. 13p. – Name: Abstract Label: Abstract Group: Ab Data: High-temperature microreactors can play a role in developing reliable, portable energy sources for off-grid remote locations, microgrid concepts, and industrial process heat. Portability and passive safety criteria tend to skew microreactor structural component designs toward complex geometries, high thermal stresses, and design bases with large numbers of startup/shutdown cycles. Current design rules, as typified by Section III of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, are less than optimal for these conditions, particularly for preliminary component designs where developers need to rapidly consider a large number of potential component configurations. This paper presents a design method targeted toward rapid, efficient evaluation of preliminary component designs using modern finite element analysis. The new method retains key connections with the ASME Code rules and design data while streamlining the design approach. This paper presents the design method, several verification examples illustrating the similarities and differences between the new method and the current ASME rules, and the application of the new approach to the evaluation of a test article mimicking key features of a heat pipe-cooled microreactor. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Nuclear Technology is the property of Taylor & Francis Ltd 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.) |
| PLink | https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=egs&AN=161273869 |
| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1080/00295450.2022.2112112 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 13 StartPage: S60 Titles: – TitleFull: A Structural Design Approach Tailored for the Rapid Preliminary Design of Microreactor Components. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Messner, Mark C. – PersonEntity: Name: NameFull: Guosheng Ye – PersonEntity: Name: NameFull: Sham, T.-L. IsPartOfRelationships: – BibEntity: Dates: – D: 02 M: 01 Text: 2023 Supplement Type: published Y: 2023 Identifiers: – Type: issn-print Value: 00295450 Numbering: – Type: volume Value: 209 Titles: – TitleFull: Nuclear Technology Type: main |
| ResultId | 1 |