{"id":{"repo_id":"mit","oai_identifier":"oai:dspace.mit.edu:1721.1/76937"},"canonical_url":"https://search.dev.ndltd.org/etd/mit/oai:dspace.mit.edu:1721.1/76937","repository":{"repo_id":"mit","name":"MIT","base_url":"https://dspace.mit.edu/oai/request"},"display":{"title":"Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures","abstract":"Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of the fuel that is coming from fission. This can lead to lower operating temperatures which will reduce the amount of fission gas release to negligible quantities, eliminate cracking, and reduce the internal energy of the fuel. Furthermore, it is hoped the UZH will be better able to attain higher burnups, partly because of the presence of the strong moderator hydrogen, and thus will help better utilize resources and reduce the volume of nuclear waste produced. In order for UZH to be viable as a fuel it is recommended that the peak central temperature of the fuel be maintained below 650°C, at which point swelling due to void formation around the uranium atoms becomes a concern. In order to keep temperature below this level it has been proposed that lead-bismuth eutectic (LBE) be used as the gap material instead of helium. In order to ensure that the properties of UZH while using a LBE gap, specifically the thermal conductivity, do not degrade to the point of the fuel not being viable, an experiment was designed and put into the MIT research reactor. The initial results show a decreasing trend in thermal conductivity, albeit with much of this change considered to be because of the many thermal cycles the experiment underwent while in the reactor.","abstract_html":"Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of the fuel that is coming from fission. This can lead to lower operating temperatures which will reduce the amount of fission gas release to negligible quantities, eliminate cracking, and reduce the internal energy of the fuel. Furthermore, it is hoped the UZH will be better able to attain higher burnups, partly because of the presence of the strong moderator hydrogen, and thus will help better utilize resources and reduce the volume of nuclear waste produced. In order for UZH to be viable as a fuel it is recommended that the peak central temperature of the fuel be maintained below 650°C, at which point swelling due to void formation around the uranium atoms becomes a concern. In order to keep temperature below this level it has been proposed that lead-bismuth eutectic (LBE) be used as the gap material instead of helium. In order to ensure that the properties of UZH while using a LBE gap, specifically the thermal conductivity, do not degrade to the point of the fuel not being viable, an experiment was designed and put into the MIT research reactor. The initial results show a decreasing trend in thermal conductivity, albeit with much of this change considered to be because of the many thermal cycles the experiment underwent while in the reactor.","abstract_has_math":false,"creators":["Ensor, Brendan M. (Brendan Melvin)"],"institution":"Massachusetts Institute of Technology","degree_name":null,"degree_level":null,"degree_discipline":null,"degree_department":"Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering.","school":null,"contributors":[],"advisors":["Gordon Kohse."],"committee_chairs":[],"committee_members":[],"year":2012,"date_issued":"2012","date_published":"2012","updated_at":"2026-07-22T22:22:04Z","subjects":["Nuclear Science and Engineering."],"languages":["eng"],"rights":["M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission."],"rights_urls":["http://dspace.mit.edu/handle/1721.1/7582"],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/1721.1/76937","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Gordon Kohse."]},{"key":"dc:contributor.department","label":"Department","values":["Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering."]},{"key":"dc:contributor.other","label":"Dc Contributor Other","values":["Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering."]},{"key":"dc:creator","label":"Author","values":["Ensor, Brendan M. 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They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission."]},{"key":"dc:rights.uri","label":"Rights URI","values":["http://dspace.mit.edu/handle/1721.1/7582"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier.uri","label":"Identifier URI","values":["http://hdl.handle.net/1721.1/76937"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.","Cataloged from PDF version of thesis.","Includes bibliographical references (p. 31-32)."]},{"key":"dc:description.abstract","label":"Abstract","values":["Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of the fuel that is coming from fission. This can lead to lower operating temperatures which will reduce the amount of fission gas release to negligible quantities, eliminate cracking, and reduce the internal energy of the fuel. Furthermore, it is hoped the UZH will be better able to attain higher burnups, partly because of the presence of the strong moderator hydrogen, and thus will help better utilize resources and reduce the volume of nuclear waste produced. In order for UZH to be viable as a fuel it is recommended that the peak central temperature of the fuel be maintained below 650°C, at which point swelling due to void formation around the uranium atoms becomes a concern. In order to keep temperature below this level it has been proposed that lead-bismuth eutectic (LBE) be used as the gap material instead of helium. In order to ensure that the properties of UZH while using a LBE gap, specifically the thermal conductivity, do not degrade to the point of the fuel not being viable, an experiment was designed and put into the MIT research reactor. The initial results show a decreasing trend in thermal conductivity, albeit with much of this change considered to be because of the many thermal cycles the experiment underwent while in the reactor."]},{"key":"dc:description.degree","label":"Dc Description Degree","values":["S.B."]},{"key":"dc:title","label":"Title","values":["Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures"]}]}],"canonical_facts":{"dc:contributor.advisor":["Gordon Kohse."],"dc:contributor.department":["Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering."],"dc:contributor.other":["Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering."],"dc:creator":["Ensor, Brendan M. (Brendan Melvin)"],"dc:date.accessioned":["2013-02-14T15:19:34Z"],"dc:date.available":["2013-02-14T15:19:34Z"],"dc:date.issued":["2012"],"dc:description":["Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.","Cataloged from PDF version of thesis.","Includes bibliographical references (p. 31-32)."],"dc:description.abstract":["Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of the fuel that is coming from fission. This can lead to lower operating temperatures which will reduce the amount of fission gas release to negligible quantities, eliminate cracking, and reduce the internal energy of the fuel. Furthermore, it is hoped the UZH will be better able to attain higher burnups, partly because of the presence of the strong moderator hydrogen, and thus will help better utilize resources and reduce the volume of nuclear waste produced. In order for UZH to be viable as a fuel it is recommended that the peak central temperature of the fuel be maintained below 650°C, at which point swelling due to void formation around the uranium atoms becomes a concern. In order to keep temperature below this level it has been proposed that lead-bismuth eutectic (LBE) be used as the gap material instead of helium. In order to ensure that the properties of UZH while using a LBE gap, specifically the thermal conductivity, do not degrade to the point of the fuel not being viable, an experiment was designed and put into the MIT research reactor. The initial results show a decreasing trend in thermal conductivity, albeit with much of this change considered to be because of the many thermal cycles the experiment underwent while in the reactor."],"dc:description.degree":["S.B."],"dc:identifier.uri":["http://hdl.handle.net/1721.1/76937"],"dc:language.iso":["eng"],"dc:publisher":["Massachusetts Institute of Technology"],"dc:rights":["M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission."],"dc:rights.uri":["http://dspace.mit.edu/handle/1721.1/7582"],"dc:subject":["Nuclear Science and Engineering."],"dc:title":["Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures"],"dc:type":["Thesis"]},"updated_at":"2026-07-22T22:22:04Z"}