The Resource Modeling of molecular and particulate transport in dry spent nuclear fuel canisters, by Andrew M. Casella, (electronic resource)

Modeling of molecular and particulate transport in dry spent nuclear fuel canisters, by Andrew M. Casella, (electronic resource)

Label
Modeling of molecular and particulate transport in dry spent nuclear fuel canisters
Title
Modeling of molecular and particulate transport in dry spent nuclear fuel canisters
Statement of responsibility
by Andrew M. Casella
Creator
Contributor
Thesis advisor
Subject
Genre
Language
eng
Summary
There are two important phenomena associated with the depressurization of a dry spent nuclear fuel canister after the formation of a through-wall pinhole breach. The first phenomenon is the release from the canister of any radioactivity that might have become suspended within the fill gas and the second is the transport of oxygen into the canister (leading to oxidation of cladding and any exposed fuel) after pressure equilibrium has been reached. In order to better quantify the effects associated with these phenomena, several models have been constructed. The first of these models determines the depressurization time of a breached canister in which no particles are suspended in the fill gas. The second model tracks the possible transport of fission gases and helium produced from alpha decay through nano-scale pathways within the spent fuel located in the canister. The third model expands the first model to track any suspended particle release from the canister and to monitor particle deposition within the breach (along with the associated flow area blockage). The fourth model uses Monte Carlo methods to remove several limitations of the third model, including particle deposition patterns, effects of particle size, and breach geometry. The results generated by these models provide a better understanding of the time-dependent behavior of a spent fuel canister that has developed a microscopic through-wall breach and may prove to be useful tools in the future monitoring and handling of spent fuel canisters
Cataloging source
MUU
http://library.link/vocab/creatorDate
1979-
http://library.link/vocab/creatorName
Casella, Andrew M.
Degree
Ph. D.
Dissertation year
2007.
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
  • Loyalka, S. K.
  • Hanson, Brady D.
http://library.link/vocab/subjectName
  • Aerosols, Radioactive
  • Nuclear fuels
  • Nuclear fuel claddings
  • Monte Carlo method
Target audience
specialized
Label
Modeling of molecular and particulate transport in dry spent nuclear fuel canisters, by Andrew M. Casella, (electronic resource)
Instantiates
Publication
Note
  • The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file
  • Title from title screen of research.pdf file (viewed on November 26, 2007
  • Vita
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Color
mixed
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Control code
182522660
Dimensions
unknown
Form of item
electronic
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Specific material designation
remote
System control number
(OCoLC)182522660
System details
Mode of access: World Wide Web
Label
Modeling of molecular and particulate transport in dry spent nuclear fuel canisters, by Andrew M. Casella, (electronic resource)
Publication
Note
  • The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file
  • Title from title screen of research.pdf file (viewed on November 26, 2007
  • Vita
Bibliography note
Includes bibliographical references
Carrier category
online resource
Carrier category code
  • cr
Carrier MARC source
rdacarrier
Color
mixed
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
Control code
182522660
Dimensions
unknown
Form of item
electronic
Media category
computer
Media MARC source
rdamedia
Media type code
  • c
Specific material designation
remote
System control number
(OCoLC)182522660
System details
Mode of access: World Wide Web

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