dc.rights.license | Users may download and share copies with attribution in accordance with a Creative Commons Attribution-Noncommercial-No Derivative Works 3.0 License. No commercial use or derivatives are permitted without the explicit approval of the author. | |
dc.contributor | Ji, Wei | |
dc.contributor | Danon, Yaron | |
dc.contributor | Caracappa, Peter | |
dc.contributor.author | Moran, Sean | |
dc.date.accessioned | 2021-11-03T08:31:43Z | |
dc.date.available | 2021-11-03T08:31:43Z | |
dc.date.created | 2016-02-09T07:49:37Z | |
dc.date.issued | 2015-12 | |
dc.identifier.uri | https://hdl.handle.net/20.500.13015/1583 | |
dc.description | December 2015 | |
dc.description | School of Engineering | |
dc.description.abstract | The Transient Reactor Test Facility is a nuclear research reactor operated by the Idaho National Laboratory. It was used for the testing of nuclear reactor fuels and materials from 1959 until 1994. It has remained inactive since its shutdown in 1994. Recently, the Department of Energy has begun preparations to restart the facility. This restart will be accompanied by many potential changes to the core and facilities. As such, a reliable model of the core is needed to facilitate the core modifications and subsequent experiment simulations. This paper details the creation of a model made to fulfill this need. | |
dc.language.iso | ENG | |
dc.publisher | Rensselaer Polytechnic Institute, Troy, NY | |
dc.relation.ispartof | Rensselaer Theses and Dissertations Online Collection | |
dc.subject | Nuclear engineering | |
dc.title | Neutronic modeling and analysis of the Transient Reactor Test Facility | |
dc.type | Electronic thesis | |
dc.type | Thesis | |
dc.digitool.pid | 176910 | |
dc.digitool.pid | 176911 | |
dc.digitool.pid | 176912 | |
dc.rights.holder | This electronic version is a licensed copy owned by Rensselaer Polytechnic Institute, Troy, NY. Copyright of original work retained by author. | |
dc.description.degree | MS | |
dc.relation.department | Dept. of Mechanical, Aerospace, and Nuclear Engineering | |