Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.
| Main Author: | |
|---|---|
| Other Authors: | |
| Format: | Thesis |
| Language: | eng |
| Published: |
Massachusetts Institute of Technology
2013
|
| Subjects: | |
| Online Access: | http://hdl.handle.net/1721.1/76937 |
| _version_ | 1826210006149627904 |
|---|---|
| author | Ensor, Brendan M. (Brendan Melvin) |
| author2 | Gordon Kohse. |
| author_facet | Gordon Kohse. Ensor, Brendan M. (Brendan Melvin) |
| author_sort | Ensor, Brendan M. (Brendan Melvin) |
| collection | MIT |
| description | Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012. |
| first_indexed | 2024-09-23T14:39:36Z |
| format | Thesis |
| id | mit-1721.1/76937 |
| institution | Massachusetts Institute of Technology |
| language | eng |
| last_indexed | 2024-09-23T14:39:36Z |
| publishDate | 2013 |
| publisher | Massachusetts Institute of Technology |
| record_format | dspace |
| spelling | mit-1721.1/769372019-04-11T07:19:24Z Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at light water reactors operating temperatures Ensor, Brendan M. (Brendan Melvin) Gordon Kohse. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering. Nuclear Science and Engineering. 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). 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. by Brendan M. Ensor. S.B. 2013-02-14T15:19:34Z 2013-02-14T15:19:34Z 2012 2012 Thesis http://hdl.handle.net/1721.1/76937 824456030 eng 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. http://dspace.mit.edu/handle/1721.1/7582 32 p. application/pdf Massachusetts Institute of Technology |
| spellingShingle | Nuclear Science and Engineering. Ensor, Brendan M. (Brendan Melvin) Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title | Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title_full | Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title_fullStr | Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title_full_unstemmed | Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title_short | Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures |
| title_sort | thermal analysis of uranium zirconium hydride fuel using a lead bismuth gap at lwr operating temperatures |
| topic | Nuclear Science and Engineering. |
| url | http://hdl.handle.net/1721.1/76937 |
| work_keys_str_mv | AT ensorbrendanmbrendanmelvin thermalanalysisofuraniumzirconiumhydridefuelusingaleadbismuthgapatlwroperatingtemperatures AT ensorbrendanmbrendanmelvin thermalanalysisofuraniumzirconiumhydridefuelusingaleadbismuthgapatlightwaterreactorsoperatingtemperatures |