Masters Theses
Keywords and Phrases
Computational fluid dynamics; Gravitational heat pipes; Porous media model; Research reactor; Volume of fluid; Wettability
Abstract
"A computational analysis of thermal-hydraulic processes in nuclear reactor systems is performed, leveraging Computational Fluid Dynamics (CFD) to advance the design and ensure the safety of nuclear reactors. Divided into two primary sections, the initial part examines thermal-hydraulic behavior in the Replacement Research Reactor (RRR) operating at 20 megawatts and evaluates potential enhancements for the Missouri University of Science and Technology Reactor (MSTR) to operate at an increased capacity of 2 megawatts from the existing 0.2 megawatts. Detailed simulations reveal insights into flow characteristics, temperature distributions, and pressure drops, highlighting the effective use of realistic and porous media modeling techniques for different reactor configurations. The second study investigates the complex flow dynamics of liquid-gas medium in sealed vessels across superhydrophilic to superhydrophobic wettability conditions. Employing CFD simulations alongside the VOF method with sharp interface accuracy, the study examines how factors such as contact angle, channel diameter, gravity, and viscosity influence flow patterns and blockages in closed environments. Results show that surface wettability and channel diameter significantly influence fluid behavior, with gravity variations further affecting flow dynamics in adiabatic, closed systems, offering insights for engineering design optimization. This comprehensive computational study explains the thermal-hydraulic processes in nuclear reactors and closed fluid systems, employing advanced CFD techniques to enhance design and safety" -- Abstract, p. iv
Advisor(s)
Usman, Shoaib
Committee Member(s)
Newkirk, Joseph William
Alam, Syed B.
Department(s)
Nuclear Engineering and Radiation Science
Degree Name
M.S. in Nuclear Engineering
Publisher
Missouri University of Science and Technology
Publication Date
Summer 2024
Pagination
xi, 72 pages
Note about bibliography
Includes_bibliographical_references_(pages 34, 65 & 71)
Rights
©2024 Mehedi Hasan Tusar , All Rights Reserved
Document Type
Thesis - Open Access
File Type
text
Language
English
Thesis Number
T 12414
Electronic OCLC #
1478139035
Recommended Citation
Tusar, Mehedi Hasan, "Computational Fluid Dynamics Analysis of Thermal-Hydraulic Phenomena in Nuclear Reactor Systems" (2024). Masters Theses. 8214.
https://scholarsmine.mst.edu/masters_theses/8214