Masters Theses

Keywords and Phrases

Thorium Molten Salt Reactor (TMSR)

Abstract

"The Generation IV International Forum placed six reactors as priority for research and development to compensate for the world's increasing energy demands. Among the six were Molten Salt Reactors (MSRs). These reactors utilize the Th/233U fuel cycle using molten fluoride or chloride salts as coolants. MSRs also have the possibility to use other fissile fuels especially with the first fleet of reactors given the low amount of Uranium-233 available commercially.

With the possibility of diverting from using 233U initially, the research presented here will benchmark 233U as a main fuel for MSRs using the Thorium Molten Salt Reactor (TMSR) designed by Billebaud Annick and her team at the Laboratory for Subatomic Particles and Cosmology in France. Uranium-235 and Plutonium-239 will then be tested as suitable initial fuels for the first fleet of TMSRs. These fuels will be compared to the reference data based on neutron flux spectra and breeding capabilities."--Abstract, page iii.

Advisor(s)

Alajo, Ayodeji Babatunde

Committee Member(s)

Mueller, Gary Edward, 1954-
Liu, Xin

Department(s)

Mining and Nuclear Engineering

Degree Name

M.S. in Nuclear Engineering

Publisher

Missouri University of Science and Technology

Publication Date

Spring 2015

Pagination

vii, 48 pages

Note about bibliography

Includes bibliographic references (pages 45-47).

Rights

© 2015 Dustin Gage Green, All rights reserved.

Document Type

Thesis - Open Access

File Type

text

Language

English

Library of Congress Subject Headings

Molten Salt Reactors
Nuclear fuels
Neutron flux -- Measurement

Thesis Number

T 10676

Electronic OCLC #

913485790

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