Skip navigation
  • Home
  • Browse
    • Communities
      & Collections
    • Browse Items by:
    • Publication Date
    • Author
    • Title
    • Subject
    • Department
  • Sign on to:
    • My MacSphere
    • Receive email
      updates
    • Edit Profile


McMaster University Home Page
  1. MacSphere
  2. Open Access Dissertations and Theses Community
  3. Open Access Dissertations and Theses
Please use this identifier to cite or link to this item: http://hdl.handle.net/11375/28366
Full metadata record
DC FieldValueLanguage
dc.contributor.advisorLuxat, John C.-
dc.contributor.advisorBuijs, Adriaan-
dc.contributor.authorBerg, Elliott-
dc.date.accessioned2023-03-17T20:34:17Z-
dc.date.available2023-03-17T20:34:17Z-
dc.date.issued2023-
dc.identifier.urihttp://hdl.handle.net/11375/28366-
dc.description.abstractA concerted effort is being coordinated among many developed countries to advance new nuclear power systems for commercial deployment. This project is called the Generation 4 International Forum. Of the design categories receiving significant attention is Molten Salt Reactors (MSRs). A shared feature is the use of molten salts at high temperature and low pressure to remove heat from the core. There are many viable MSR design configurations and current designs vary considerably, not only in the general design concept but within design concepts as well. The primary objective of this study is to optimize, on a cost basis, the salt composition and key geometric parameters of MSR design concepts. A novel framework is developed to relate reactor design/construction conditions as well as specific configuration parameters to cost. The evaluation is broad in scope and is therefore divided into several metrics of performance, direct cost, waste, safety, proliferation, modularity and feasibility (technical difficulty). Two reactor classes are examined, the salt-cooled, pebble-bed Fluoride High-temperature Reactor (FHR) and the graphite-moderated, circulating-fuel reactor. Both design evaluations involve numerous analyses to generate data used in the evaluation, such as the calculation of temperature reactivity feedback coefficients and heat exchanger size optimization. The FHR analysis includes maximum fuel temperature calculations and depletion simulations that aim to model on-line refuelling. The circulating-fuel reactor analysis includes the use of novel methods to optimize the xenon removal rate and optimize the salt channel pitch. The cost evaluation was executed with both fixed values and probabilistic distributions applied to many consequential inputs. The results obtained using fixed values provide useful insights into the effect design parameters have on cost, while uncertainty analysis provides estimates of cost uncertainty, both overall and between configurations. Sensitivity analysis breaks down the cost uncertainty into component parts. This work aims to deepen the understanding of the costs and trade-offs associated with numerous design characteristics.en_US
dc.language.isoenen_US
dc.subjectMolten Salt Reactoren_US
dc.subjectFluoride High-temperature Reactoren_US
dc.subjectCost-based optimizationen_US
dc.subjectSalt selectionen_US
dc.subjectGeometric optimizationen_US
dc.subjectUncertainty analysisen_US
dc.subjectSensitivity analysisen_US
dc.subjectNeutronics simulationsen_US
dc.titleMethod and Implementation of Geometric Optimization and Salt Selection of Molten Salt Reactors.en_US
dc.typeThesisen_US
dc.contributor.departmentEngineering Physics and Nuclear Engineeringen_US
dc.description.degreetypeDissertationen_US
dc.description.degreeCandidate in Philosophyen_US
dc.description.layabstractMolten Salt Reactors (MSRs) often refer to design concepts that use liquid salt at high temperature and low pressure to remove heat from the core. Within this definition of MSRs, a large range of design concepts with many fundamental differences are viable and have been explored. This thesis aims to assess, on a cost basis, the feasibility of a large range of potential configurations. Two reactor design concepts, one with fuel encased in graphite pebbles and salt coolant and another consisting of salt with dissolved uranium fuel that circulates through a graphite-moderated core are analysed. Through a shared framework, the data generated from the analyses are used to relate reactor design/construction conditions as well as specific configuration parameters to cost. Probabilistic distributions are applied to many parameters consequential to determining cost in order to perform uncertainty and sensitivity analysis.en_US
Appears in Collections:Open Access Dissertations and Theses

Files in This Item:
File Description SizeFormat 
Berg_Elliott_2023March_EngineeringPhysics.pdf
Access is allowed from: 2024-03-12
8.84 MBAdobe PDFView/Open
Show simple item record Statistics


Items in MacSphere are protected by copyright, with all rights reserved, unless otherwise indicated.

Sherman Centre for Digital Scholarship     McMaster University Libraries
©2022 McMaster University, 1280 Main Street West, Hamilton, Ontario L8S 4L8 | 905-525-9140 | Contact Us | Terms of Use & Privacy Policy | Feedback

Report Accessibility Issue