Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.
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| Other Authors: | |
| Format: | Thesis |
| Language: | eng |
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Massachusetts Institute of Technology
2013
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| Online Access: | http://hdl.handle.net/1721.1/82456 |
| _version_ | 1826191962465632256 |
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| author | Fray, Elliott Shepard |
| author2 | Ronald G. Ballinger. |
| author_facet | Ronald G. Ballinger. Fray, Elliott Shepard |
| author_sort | Fray, Elliott Shepard |
| collection | MIT |
| description | Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013. |
| first_indexed | 2024-09-23T09:04:02Z |
| format | Thesis |
| id | mit-1721.1/82456 |
| institution | Massachusetts Institute of Technology |
| language | eng |
| last_indexed | 2024-09-23T09:04:02Z |
| publishDate | 2013 |
| publisher | Massachusetts Institute of Technology |
| record_format | dspace |
| spelling | mit-1721.1/824562019-04-10T20:30:50Z Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor Fray, Elliott Shepard Ronald G. Ballinger. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering. Nuclear Science and Engineering. Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013. Cataloged from PDF version of thesis. Includes bibliographical references (pages 176-179). This study has extended the development of an exciting technology which promises to enable the Pb-Bi eutectic cooled reactors to operate at temperatures up to 650-700°C. This new technology is a functionally graded composite steel which resists high temperature LBE corrosion. This composite steel consists of a Fel2Cr2Si protective layer weld overlaid on a T91 steel and then drawn to fuel cladding and piping material. A series of tests and materials analysis were performed on the composite piping material. These tests / analysis included microstructural characterization, heat treatment optimization, creep and tensile testing, diffusion testing, and long term static corrosion tests. Although the composite fuel cladding was not available at the time of this study, all of the results from the piping material characterization are directly applicable to the fuel cladding material. It has been shown that the heat treated composite piping material exhibits mechanical properties in excess of the ASTM minimum standard for T91. This material also exhibits a conservative corrosion rate of< 22pm/yr in static Pb-Bi eutectic. This low corrosion rate will enable fuel cladding to have a 3.6 year lifetime and piping material a 36 year lifetime, if the static corrosion rate is equivalent to the flowing corrosion rate. This material has also been shown to have a very slow diffusion rate for chromium, with a chromium inter-diffusion zone of < 35um over the lifetime of the nuclear reactor. There still however exist several challenges to implementing this technology. The challenges include resolving the issue of cracking of the Fel2Cr2Si layer during tube drawing and increasing the high temperature stress / creep resistance of the structural T91 layer. by Elliott Shepard Fray. S.M. 2013-11-18T19:25:28Z 2013-11-18T19:25:28Z 2013 Thesis http://hdl.handle.net/1721.1/82456 863062633 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 187 pages application/pdf Massachusetts Institute of Technology |
| spellingShingle | Nuclear Science and Engineering. Fray, Elliott Shepard Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title | Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title_full | Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title_fullStr | Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title_full_unstemmed | Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title_short | Materials testing and development of functionally graded composite fuel cladding and piping for the Lead-Bismuth cooled nuclear reactor |
| title_sort | materials testing and development of functionally graded composite fuel cladding and piping for the lead bismuth cooled nuclear reactor |
| topic | Nuclear Science and Engineering. |
| url | http://hdl.handle.net/1721.1/82456 |
| work_keys_str_mv | AT frayelliottshepard materialstestinganddevelopmentoffunctionallygradedcompositefuelcladdingandpipingfortheleadbismuthcoolednuclearreactor |