Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
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| Format: | Thesis |
| Language: | eng |
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Massachusetts Institute of Technology
2020
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| Online Access: | https://hdl.handle.net/1721.1/123360 |
| _version_ | 1811085473546764288 |
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| author | Labossière-Hickman. Travis J. |
| author2 | Benoit Forget and Kord Smith. |
| author_facet | Benoit Forget and Kord Smith. Labossière-Hickman. Travis J. |
| author_sort | Labossière-Hickman. Travis J. |
| collection | MIT |
| description | This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. |
| first_indexed | 2024-09-23T13:10:09Z |
| format | Thesis |
| id | mit-1721.1/123360 |
| institution | Massachusetts Institute of Technology |
| language | eng |
| last_indexed | 2024-09-23T13:10:09Z |
| publishDate | 2020 |
| publisher | Massachusetts Institute of Technology |
| record_format | dspace |
| spelling | mit-1721.1/1233602020-01-09T03:15:14Z Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods Modeling and simulation of TREAT using modern neutron transport methods Labossière-Hickman. Travis J. Benoit Forget and Kord Smith. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Nuclear Science and Engineering. This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2019 Cataloged from student-submitted PDF version of thesis. Includes bibliographical references (pages 111-113). The Transient Reactor Test Facility (TREAT) has regained the interest of the nuclear engineering community in recent years. While TREAT's design makes it uniquely suited to transient fuel testing, it also makes the reactor very challenging to model and simulate. In this thesis, we build a Monte Carlo model of TREAT's Minimum Critical Mass core to examine the effects of fuel impurities, calculate a reference solution, and analyze a number of multigroup cross section generation approaches. Several method of characteristics (MOC) simulations employing these cross sections are then converged in space and angle, corrected for homogenization, and compared to the Monte Carlo reference solution. The thesis concludes with recommendations for future analysis of TREAT using MOC. by Travis J. Labossière-Hickman. S.M. S.M. Massachusetts Institute of Technology, Department of Nuclear Science and Engineering 2020-01-08T19:33:28Z 2020-01-08T19:33:28Z 2019 2019 Thesis https://hdl.handle.net/1721.1/123360 1134766149 eng MIT theses are protected by copyright. They may be viewed, downloaded, or printed from this source but further reproduction or distribution in any format is prohibited without written permission. http://dspace.mit.edu/handle/1721.1/7582 113 pages application/pdf Massachusetts Institute of Technology |
| spellingShingle | Nuclear Science and Engineering. Labossière-Hickman. Travis J. Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title | Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title_full | Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title_fullStr | Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title_full_unstemmed | Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title_short | Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods |
| title_sort | modeling and simulation of the transient reactor test facility using modern neutron transport methods |
| topic | Nuclear Science and Engineering. |
| url | https://hdl.handle.net/1721.1/123360 |
| work_keys_str_mv | AT labossierehickmantravisj modelingandsimulationofthetransientreactortestfacilityusingmodernneutrontransportmethods AT labossierehickmantravisj modelingandsimulationoftreatusingmodernneutrontransportmethods |