The effect of low dose-rate irradiation on the microstructure of 304 stainless steel. Metadata
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Title
- Main Title The effect of low dose-rate irradiation on the microstructure of 304 stainless steel.
Creator
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Author: Cole, J. I.Creator Type: Personal
Contributor
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Sponsor: United States. Department of Energy.Contributor Type: OrganizationContributor Info: US Department of Energy (United States)
Publisher
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Name: Argonne National LaboratoryPlace of Publication: IllinoisAdditional Info: Argonne National Lab., IL (United States)
Date
- Creation: 1998-12-02
Language
- English
Description
- Content Description: Changes in mechanical and corrosion properties caused by the development of radiation-induced microstructure have relevance to the aging and lifetime extension of light water reactors (LWR's). However, much of the current data related to microstructural development in irradiated metals are generated from studies carried out at much higher dose-rates than encountered in LWR's. An opportunity exists to study the influence of low dose-rate irradiation on microstructural development for a variety of structural and surveillance materials extracted from the experimental breeder reactor EBR-II. In this study, irradiated 304 stainless steel hexagonal ''hex'' duct material is examined in order to compare microstructure in the dose-rate range of 10{sup {minus}7}-10{sup {minus}9} dpakec. The samples, taken from the reflector locations in EBR-II, experienced a total dose between 10 and 12 dpa at a temperature of {approximately}375 C. Transmission electron microscopy (TEM) results reveal that there is a moderate dose-rate effect on microstructural development for samples irradiated in the range of 2 x 10{sup {minus}8} to 4 x 10{sup {minus}8} dpa/sec, however a substantial dose rate-effect exists between dose-rates of 2 x 10{sup {minus}8} and 1 x 10{sup {minus}9} dpa/sec Transmission electron microscopy (TEM) results will detail the development of the microstructure in terms of radiation-induced cavities, dislocations, and precipitates.
- Physical Description: 9 p.
Subject
- Keyword: Ebr-2 Reactor
- STI Subject Categories: 36 Materials Science
- Keyword: Radiation Effects
- Keyword: Stainless Steel-304
- Keyword: Dose Rates
- Keyword: Microstructure
- Keyword: Morphological Changes
- Keyword: Service Life
- Keyword: Water Cooled Reactors
- STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
Source
- Conference: Materials Research Society 1998 Fall Meeting, Boston, MA (US), 11/30/1998--12/04/1998
Collection
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Name: Office of Scientific & Technical Information Technical ReportsCode: OSTI
Institution
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Name: UNT Libraries Government Documents DepartmentCode: UNTGD
Resource Type
- Article
Format
- Text
Identifier
- Report No.: ANL/ED/CP-96583
- Grant Number: W-31109-ENG-38
- Office of Scientific & Technical Information Report Number: 10831
- Archival Resource Key: ark:/67531/metadc621019
Note
- Display Note: INIS; OSTI as DE00010831
- Display Note: Medium: P; Size: 9 pages