Irradiation induced creep behavior of H-451 graphite
Saved in:
| Title: | Irradiation induced creep behavior of H-451 graphite |
|---|---|
| Authors: | Burchell, Timothy D.1 burchelltd@ornl.gov |
| Source: | Journal of Nuclear Materials. Oct2008, Vol. 381 Issue 1/2, p46-54. 9p. |
| Subjects: | Irradiation, Creep (Materials), Graphite |
| Abstract: | Abstract: The application of a creep model previously applied to compressive creep data for H-451 irradiated at 900°C (13.7 and 20.8MPa) has been extended to compressive creep data for H-451 irradiated at 600°C (13.7 and 20.8MPa). The basis of the creep model is discussed and the experimental data required to evaluate the terms in the creep model are reported and discussed. The model, which corrects the true (crystal) creep strain for the effect of creep on the dimensional change component of the creep specimen, is shown to be a good fit to the data. Creep strain data for H-451 graphite irradiated at 900°C under a tensile stress of 6MPa are also reported, along with the required experimental data to evaluate the terms in the creep model. The model is shown to inadequately represent the high dose (post volume turn-around) H-451 tensile creep strain data. Reasons for the models limitation are discussed and an approach to a potentially improved graphite irradiation creep model is suggested. [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 |
|---|---|
| Header | DbId: egs DbLabel: Engineering Source An: 34982074 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
| IllustrationInfo | |
| Items | – Name: Title Label: Title Group: Ti Data: Irradiation induced creep behavior of H-451 graphite – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Burchell%2C+Timothy+D%2E%22">Burchell, Timothy D.</searchLink><relatesTo>1</relatesTo><i> burchelltd@ornl.gov</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Journal+of+Nuclear+Materials%22">Journal of Nuclear Materials</searchLink>. Oct2008, Vol. 381 Issue 1/2, p46-54. 9p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Irradiation%22">Irradiation</searchLink><br /><searchLink fieldCode="DE" term="%22Creep+%28Materials%29%22">Creep (Materials)</searchLink><br /><searchLink fieldCode="DE" term="%22Graphite%22">Graphite</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: Abstract: The application of a creep model previously applied to compressive creep data for H-451 irradiated at 900°C (13.7 and 20.8MPa) has been extended to compressive creep data for H-451 irradiated at 600°C (13.7 and 20.8MPa). The basis of the creep model is discussed and the experimental data required to evaluate the terms in the creep model are reported and discussed. The model, which corrects the true (crystal) creep strain for the effect of creep on the dimensional change component of the creep specimen, is shown to be a good fit to the data. Creep strain data for H-451 graphite irradiated at 900°C under a tensile stress of 6MPa are also reported, along with the required experimental data to evaluate the terms in the creep model. The model is shown to inadequately represent the high dose (post volume turn-around) H-451 tensile creep strain data. Reasons for the models limitation are discussed and an approach to a potentially improved graphite irradiation creep model is suggested. [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.) |
| PLink | https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=egs&AN=34982074 |
| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1016/j.jnucmat.2008.07.022 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 9 StartPage: 46 Subjects: – SubjectFull: Irradiation Type: general – SubjectFull: Creep (Materials) Type: general – SubjectFull: Graphite Type: general Titles: – TitleFull: Irradiation induced creep behavior of H-451 graphite Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Burchell, Timothy D. IsPartOfRelationships: – BibEntity: Dates: – D: 31 M: 10 Text: Oct2008 Type: published Y: 2008 Identifiers: – Type: issn-print Value: 00223115 Numbering: – Type: volume Value: 381 – Type: issue Value: 1/2 Titles: – TitleFull: Journal of Nuclear Materials Type: main |
| ResultId | 1 |