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dc.creatorYilmaz, Fatma
dc.date.accessioned2012-06-07T15:49:21Z
dc.date.available2012-06-07T15:49:21Z
dc.date.created2002
dc.date.issued2002
dc.identifier.urihttps://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-Y4
dc.descriptionDue to the character of the original source materials and the nature of batch digitization, quality control issues may be present in this document. Please report any quality issues you encounter to digital@library.tamu.edu, referencing the URI of the item.en
dc.descriptionIncludes bibliographical references (leaves 61-64).en
dc.descriptionIssued also on microfiche from Lange Micrographics.en
dc.description.abstractThe objective of this research is to go through the technical review of how the body of information relating to the in-reactor behavior of structural materials of Experimental Breeder Reactor-II (EBR-II) and BN350 are associated. Such an effort would lead to reviewing and combining the data from both sides as it concerns important issues for the Light Water Reactor (LWR) and fast reactor communities. The most important issue is the applicability of the BN350 and EBR-II data for the studies on prolonging the lifetime of LWRs. EBR-II and BN350 are sodium cooled fast reactors that had operated for more than twenty-five years. Studies to review and compile the existing reactor materials data for the purpose of this thesis were completed both in the U.S. and in Kazakhstan. The compilation, comparison and combination of the data was done by developing several databases using SQL software. The BN350 data on ultimate tensile strength and total elongation depending on swelling have been shown. The BN350 data is over a large swelling range (0-15 %) and reveals total consumption of ductility and strength as the amount of swelling reaches high values. The BN350 data is an important example supporting other studies that show a dominant correlation between swelling and mechanical property loss in the high swelling range (>10 %). Different forms of axial strain data from both reactors, which could be of use in reactor control and decommissioning studies, are presented, as well. The swelling formulations developed for Russian and American austenitic steels before reaching steady-state conditions are compared, and possible applications of the formulation for Russian steels to some compositionally similar American steels have been discussed. The effects of slight composition and metallurgical condition differences on swelling are stated to explain the possible differences between the data points of American steel and the predictions for the corresponding Russian steel. Some of the compiled data on ferritic/martensitic steels are presented showing their better mechanical property and swelling behaviors in the EBR-II and BN350 exposure conditions.en
dc.format.mediumelectronicen
dc.format.mimetypeapplication/pdf
dc.language.isoen_US
dc.publisherTexas A&M University
dc.rightsThis thesis was part of a retrospective digitization project authorized by the Texas A&M University Libraries in 2008. Copyright remains vested with the author(s). It is the user's responsibility to secure permission from the copyright holder(s) for re-use of the work beyond the provision of Fair Use.en
dc.subjectnuclear engineering.en
dc.subjectMajor nuclear engineering.en
dc.titleReactor materials study of EBR-II and BN350en
dc.typeThesisen
thesis.degree.disciplinenuclear engineeringen
thesis.degree.nameM.S.en
thesis.degree.levelMastersen
dc.type.genrethesisen
dc.type.materialtexten
dc.format.digitalOriginreformatted digitalen


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