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dc.creatorBigler, Mark Andrew
dc.date.accessioned2012-06-07T22:43:49Z
dc.date.available2012-06-07T22:43:49Z
dc.date.created1996
dc.date.issued1996
dc.identifier.urihttps://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-B52
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.en
dc.descriptionIssued also on microfiche from Lange Micrographics.en
dc.description.abstractA neutronic evaluation of the Texas A&M University Nuclear Science Center Reactor (TAMU NSCR) using the General Atomic Company (GA) low enrichment uranium (LEU 30-20 fuel was performed to determine the feasibility of this type of fuel. To perform this evaluation, the WIMSD4m transport code and DIF3D diffusion code were utilized. These codes were provided by Argonne National Laboratory (ANL). WIMSD4m was used to calculate macroscopic cross-sections for the various core materials and DIF3D was used to calculate the effective multiplication factor and thermal neutron flux for various core configurations. In order to benchmark these codes and the core model used to evaluate the proposed LEU 30-20 core, the current FLIP core was first modeled. Various neutronic parameters, such as excess reactivity, shutdown margin, critical rod height and control rod worths were calculated using the core model and codes, and the results compared with actual experimental results for the FLIP core. Once the core model and codes were validated, the core model was modified using LEU 30-20 fuel and an optimum core configuration obtained which satisfied certain design criteria, including values for excess reactivity, shutdown margin and thermal neutron flux. In addition to modeling the LEU 30-20 core, a control rod model was developed to generate effective macroscopic cross-sections for the control rod materials in the core, based on previous work in this area performed at ANL. The results of this analysis indicate the feasibility of converting the TAMU NSCR to GA LEU 30-20 fuel.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.subjecten
dc.titleNeutronic evaluation of LEU 30-20 fuel for the Texas A&M Nuclear Science Center Reactoren
dc.typeThesisen
thesis.degree.disciplineen
thesis.degree.nameM.S.en
thesis.degree.levelMastersen
dc.type.genrethesisen
dc.type.materialtexten
dc.format.digitalOriginreformatted digitalen


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