{"id":{"repo_id":"mit","oai_identifier":"oai:dspace.mit.edu:1721.1/123360"},"canonical_url":"https://search.dev.ndltd.org/etd/mit/oai:dspace.mit.edu:1721.1/123360","repository":{"repo_id":"mit","name":"MIT","base_url":"https://dspace.mit.edu/oai/request"},"display":{"title":"Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods","abstract":"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.","abstract_html":"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.","abstract_has_math":false,"creators":["Labossière-Hickman. Travis J."],"institution":"Massachusetts Institute of Technology","degree_name":"Master","degree_level":null,"degree_discipline":null,"degree_department":"Massachusetts Institute of Technology. Department of Nuclear Science and Engineering","school":null,"contributors":[],"advisors":["Benoit Forget and Kord Smith."],"committee_chairs":[],"committee_members":[],"year":2019,"date_issued":"2019","date_published":"2019","updated_at":"2026-07-22T22:21:46Z","subjects":["Nuclear Science and Engineering."],"languages":["eng"],"rights":["MIT theses are protected by copyright. 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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."]},{"key":"dc:description.degree","label":"Dc Description Degree","values":["S.M."]},{"key":"dc:title","label":"Title","values":["Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods"]}]}],"canonical_facts":{"dc:contributor.advisor":["Benoit Forget and Kord Smith."],"dc:contributor.department":["Massachusetts Institute of Technology. Department of Nuclear Science and Engineering","NucEng"],"dc:contributor.other":["Massachusetts Institute of Technology. Department of Nuclear Science and Engineering."],"dc:creator":["Labossière-Hickman. 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