Modeling and simulation of The Transient Reactor Test Facility using modern neutron transport methods
Name
1134766149-MIT.pdf
Size
4.85 MB
Format
Adobe PDF
Checksum (MD5)
1c5027fd1009c7b5852ce16bd593bdb6
Author(s)
Labossière-Hickman. Travis J.
Advisor(s)
Benoit Forget and Kord Smith.
Alternative Title
Modeling and simulation of TREAT using modern neutron transport methods
Date Issued
2019
Publisher
Massachusetts Institute of Technology
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.
Description
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).
Subjects
Nuclear Science and Engineering.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
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.
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