Radioxenon generation using highly enriched uranium Public Deposited

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/t435gh57r

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  • This work focuses on the generation and collection of four specific radioxenon isotopes; xenon-131m, xenon-133m, xenon-133 and xenon-135. These nuclides are created by fissioning a highly enriched uranium sample using a thermal neutron source from a university research reactor. The three main aspects of this work include: (1) Conducting preliminary calculations of xenon fission products; (2) Designing and constructing an apparatus for sample irradiation and gas delivery; and (3) Generating xenon gas from a reusable apparatus that will allow for multiple radioxenon production events. Also included in the following work is a comprehensive background on information pertaining to the works included. This information should aid 3 individuals unfamiliar in the nuclear field a background understanding of the topics discussed. The preliminary calculations performed are used to find values such as flux, fission product percentages created, dose, as well as a range of other pertinent information. The calculations have been performed primarily to aid in the generation of the xenon isotopes, but also to obtain the necessary approvals to perform the irradiation experiment at Oregon State University. The design section of this work includes detailed information on the fabrication of the apparatus used to generate the fission gas products. This includes blueprints, manufacturing techniques, parts list, as well as a final assembled apparatus figure to allow for easy reproduction of the system. The fission chamber device utilized for the irradiation of the HEU material is of a flange design constructed of aluminum. The entire system has been designed for irradiation outside the reactor bioshield, utilizing a neutron beamport adjacent to the reactor core. This work also includes an analysis of the xenon isotopes created to verify the experimental success. Using the XEPHWICH detector developed at Oregon State University, the xenon isotopes were counted and identified for verification of activities and correct yield percentages. The generation system efficiency is also determined to account for system losses. With an accurate approximation on the generation efficiency, this fission gas generation system can also be used to create radioxenon isotopes for the calibration of specific detector designs.
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  • description.provenance : Submitted by Anthony Elliott (ellioant@onid.orst.edu) on 2008-07-02T02:30:33Z No. of bitstreams: 1 xenon thesis june 17.pdf: 1660002 bytes, checksum: c0130cdb1120f1e38480603f9bbe74ef (MD5)
  • description.provenance : Made available in DSpace on 2008-08-27T20:31:39Z (GMT). No. of bitstreams: 1 xenon thesis june 17.pdf: 1660002 bytes, checksum: c0130cdb1120f1e38480603f9bbe74ef (MD5)
  • description.provenance : Approved for entry into archive by Linda Kathman(linda.kathman@oregonstate.edu) on 2008-08-27T20:31:39Z (GMT) No. of bitstreams: 1 xenon thesis june 17.pdf: 1660002 bytes, checksum: c0130cdb1120f1e38480603f9bbe74ef (MD5)
  • description.provenance : Approved for entry into archive by Julie Kurtz(julie.kurtz@oregonstate.edu) on 2008-08-18T22:12:59Z (GMT) No. of bitstreams: 1 xenon thesis june 17.pdf: 1660002 bytes, checksum: c0130cdb1120f1e38480603f9bbe74ef (MD5)

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