The Resource Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee
Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee
Resource Information
The item Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee represents a specific, individual, material embodiment of a distinct intellectual or artistic creation found in University of Missouri-St. Louis Libraries.This item is available to borrow from all library branches.
Resource Information
The item Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee represents a specific, individual, material embodiment of a distinct intellectual or artistic creation found in University of Missouri-St. Louis Libraries.
This item is available to borrow from all library branches.
- Summary
- One of the most severe accidents anticipated for the Very High Temperature Reactor (VHTR) is an air ingress accident caused by a pipe break, where the reactor vessel and core become fully immersed in air as the core temperature rises potentially reaching 1873 K. Graphite oxidation is predicted to be severe under these conditions. Gasification of graphite impacts its geometry and reduces thermal and mechanical properties, thus affecting the safe performance and shortening the service-life of components constructed of graphite. We have studied the oxidation rate of several nuclear-grade and matrix-grade graphites including NBG-18 and IG-110 as well as GKrS, respectively. Oxidation data was collected thermogravimetrically for air ingress accident scenarios from 873 to 1873 K using a Thermax700® thermogravimetric analyzer. A semi-empirical Arrhenius rate equation was developed for the kinetic regime for each graphite grade. The activation energy for the matrix-grade graphite was within the limited historically reported values while the activation energy of nuclear-grade graphite was determined to be well within literature values. The surfaces of oxidized graphite samples were further characterized by SEM, EDS, FTIR and XPS
- Language
- eng
- Extent
- 1 online resource (viii, 107 pages)
- Note
-
- Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka
- Includes vita
- Label
- Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios
- Title
- Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios
- Statement of responsibility
- by Yoonjo J. Lee
- Title variation
- Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios
- Language
- eng
- Summary
- One of the most severe accidents anticipated for the Very High Temperature Reactor (VHTR) is an air ingress accident caused by a pipe break, where the reactor vessel and core become fully immersed in air as the core temperature rises potentially reaching 1873 K. Graphite oxidation is predicted to be severe under these conditions. Gasification of graphite impacts its geometry and reduces thermal and mechanical properties, thus affecting the safe performance and shortening the service-life of components constructed of graphite. We have studied the oxidation rate of several nuclear-grade and matrix-grade graphites including NBG-18 and IG-110 as well as GKrS, respectively. Oxidation data was collected thermogravimetrically for air ingress accident scenarios from 873 to 1873 K using a Thermax700® thermogravimetric analyzer. A semi-empirical Arrhenius rate equation was developed for the kinetic regime for each graphite grade. The activation energy for the matrix-grade graphite was within the limited historically reported values while the activation energy of nuclear-grade graphite was determined to be well within literature values. The surfaces of oxidized graphite samples were further characterized by SEM, EDS, FTIR and XPS
- Cataloging source
- MUU
- http://library.link/vocab/creatorDate
- 1983-
- http://library.link/vocab/creatorName
- Lee, Yoonjo J.
- Degree
- Ph. D.
- Dissertation note
- Thesis
- Dissertation year
- 2016.
- Government publication
- government publication of a state province territory dependency etc
- Granting institution
- University of Missouri--Columbia
- Illustrations
- illustrations
- Index
- no index present
- Literary form
- non fiction
- Nature of contents
-
- dictionaries
- bibliography
- theses
- http://library.link/vocab/relatedWorkOrContributorName
-
- Ghosh, Tushar K.
- Loyalka, S. K.
- http://library.link/vocab/subjectName
-
- Nuclear reactors
- Graphite
- Oxidation
- Materials at high temperatures
- Label
- Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee
- Note
-
- Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka
- Includes vita
- Bibliography note
- Includes bibliographical references
- Carrier category
- online resource
- Carrier category code
-
- cr
- Carrier MARC source
- rdacarrier
- Content category
- text
- Content type code
-
- txt
- Content type MARC source
- rdacontent
- Control code
- 989737607
- Extent
- 1 online resource (viii, 107 pages)
- Form of item
- online
- Media category
- computer
- Media MARC source
- rdamedia
- Media type code
-
- c
- Other physical details
- illustrations
- Specific material designation
- remote
- System control number
- (OCoLC)989737607
- Label
- Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee
- Note
-
- Dissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka
- Includes vita
- Bibliography note
- Includes bibliographical references
- Carrier category
- online resource
- Carrier category code
-
- cr
- Carrier MARC source
- rdacarrier
- Content category
- text
- Content type code
-
- txt
- Content type MARC source
- rdacontent
- Control code
- 989737607
- Extent
- 1 online resource (viii, 107 pages)
- Form of item
- online
- Media category
- computer
- Media MARC source
- rdamedia
- Media type code
-
- c
- Other physical details
- illustrations
- Specific material designation
- remote
- System control number
- (OCoLC)989737607
Library Locations
-
St. Louis Mercantile LibraryBorrow it1 University Blvd, St. Louis, MO, 63121, US38.710138 -90.311107
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-
University ArchivesBorrow it703 Lewis Hall, Columbia, MO, 65211, US
-
University of Missouri-St. Louis Libraries DepositoryBorrow it2908 Lemone Blvd, Columbia, MO, 65201, US38.919360 -92.291620
-
University of Missouri-St. Louis Libraries DepositoryBorrow it2908 Lemone Blvd, Columbia, MO, 65201, US38.919360 -92.291620
-
Ward E Barnes Education LibraryBorrow it8001 Natural Bridge Rd, St. Louis, MO, 63121, US38.707079 -90.311355
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<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.umsl.edu/portal/Oxidation-of-nuclear--and-matrix-grade-graphite/ZEdaOvsr_38/" typeof="Book http://bibfra.me/vocab/lite/Item"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.umsl.edu/portal/Oxidation-of-nuclear--and-matrix-grade-graphite/ZEdaOvsr_38/">Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios, by Yoonjo J. Lee</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.umsl.edu/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.umsl.edu/">University of Missouri-St. Louis Libraries</a></span></span></span></span></div>
