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Massachusetts Institute of Technology

Neutronic-Thermal Simulation of Micro Reactor Designs for the Purpose of Analyzing the Impact of Thermal Expansion and Hydrogen Migration in Metal Hydride Moderator

Abstract

dc:description.abstract

The recent increased interest in microreactor designs has presented the opportunity to take advantage of the smaller core dimensions to perform steady state neutronic-thermal coupled simulation with the inclusion of an additional physics system. This work accomplishes this, by adding thermal expansion and zirconium hydride-based hydrogen diffusion to the neutronic-thermal simulation of multiple heat pipe microreactor designs. Microreactors’ smaller cores are inherently characterized by more leakage than gigawatt-scale reactor cores. The inclusion of thermal expansion’s representation in the coupling system may reveal neutronic or thermal impacts of geometric expansion that have yet to be noted for these smaller scale geometries. This is the impetus for the work on thermal expansion. The work on hydrogen diffusion is inspired by the common use of zirconium hydride in microreactor designs as a moderator. This material provides high density of hydrogen with high melting point, but features a well documented increase in mobility of hydrogen within the zirconium lattice at high temperatures. Coupling this migration of hydrogen within the neutronic-thermal simulation is performed in order to identify and analyze neutronic and thermal impacts due to the movement of hydrogen within the moderator. Additionally, a heat pipe failure case is simulated for each microreactor geometry studied, aimed to analyze the impacts of multipipe failure on both thermal expansion and hydrogen diffusion, as well as their downstream neutronic-thermal effects.

Degree

thesis:*
Name thesis:degree_name
Doctoral
Department dc:contributor.department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Grantor dc:publisher
Massachusetts Institute of Technology
Year dc:date.issued
2024

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Kendrick, W. Reed
Advisor dc:contributor.advisor
  • Forget, Benoit

Rights

dc:rights
Statement dc:rights
  • Attribution-NonCommercial-NoDerivatives 4.0 International (CC BY-NC-ND 4.0)
  • Copyright retained by author(s)

Identifiers

dc:identifier.*
Handle dc:identifier.uri
https://hdl.handle.net/1721.1/157171
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/157171

Chain of custody

source
Harvested from
MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Kendrick, W. Reed. Neutronic-Thermal Simulation of Micro Reactor Designs for the Purpose of Analyzing the Impact of Thermal Expansion and Hydrogen Migration in Metal Hydride Moderator. Massachusetts Institute of Technology, 2024. https://hdl.handle.net/1721.1/157171