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1. OECD/NRC Benchmark Based on NUPEC PWR Subchannel and Bundle Tests (PSBT) - Analysis Using Subchannel Code CTF and System Code TRACE

open_access
Open Access
Author:
Rubin, Adam
Title:
OECD/NRC Benchmark Based on NUPEC PWR Subchannel and Bundle Tests (PSBT) - Analysis Using Subchannel Code CTF and System Code TRACE
Graduate Program:
Nuclear Engineering
Keywords:
TRACE
CTF
PSBT
File:
Download Adam_Rubin_Master_Thesis.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

5. Interfacial Area Transport Equation for Vertical and Horizontal Bubbly Flows and its Application to the TRACE Code

open_access
Open Access
Author:
Talley, Justin D
Title:
Interfacial Area Transport Equation for Vertical and Horizontal Bubbly Flows and its Application to the TRACE Code
Graduate Program:
Nuclear Engineering
Keywords:
horizontal two-phase flow
interfacial area transport equation
four-sensor conductivity probe
TRACE
File:
Download Talley_Dissertation_Final.pdf
Committee Members:
Seungjin Kim, Dissertation Advisor/Co-Advisor
Fan Bill B Cheung, Committee Member
John Harlan Mahaffy, Committee Member
Seong H Kim, Committee Member
John R Buchanan Jr, Special Member

7. Implementation of the Interfacial Area Transport Equation in TRACE for Boiling Two-Phase Flows

open_access
Open Access
Author:
Bernard, Matthew Stephen
Title:
Implementation of the Interfacial Area Transport Equation in TRACE for Boiling Two-Phase Flows
Graduate Program:
Nuclear Engineering
Keywords:
TRACE
ai
interfacial area concentration
interfacial area transport equation
IATE
conductivity probe
two-phase flow
boiling
one-group IATE
two-group IATE
File:
Download 1-M._Bernard_Thesis.pdf
Committee Members:
Seungjin Kim, Dissertation Advisor/Co-Advisor
Seungjin Kim, Committee Chair/Co-Chair
John Harlan Mahaffy, Committee Member
Kostadin Nikolov Ivanov, Committee Member
Francesco Costanzo, Committee Member
Chris Hoxie, Special Member

8. Comparison of Water, Helium, and Carbon Dioxide as Coolants for Next Generation Power Plants using TRACE

open_access
Open Access
Author:
Garrett, Grant Robert
Title:
Comparison of Water, Helium, and Carbon Dioxide as Coolants for Next Generation Power Plants using TRACE
Graduate Program:
Nuclear Engineering
Keywords:
Generation IV Reactors
Water
Helium
Carbon Dioxide
Thermal-Hydraulic Simulation
TRACE
SNAP
Fusion Reactors
File:
Download Grant_Garrett_Master_s_Thesis.pdf
Committee Members:
Justin Kyle Watson, Thesis Advisor/Co-Advisor

9. Fission matrix methods for temperature and control feedback of small nuclear systems

open_access
Open Access
Author:
Rau, Adam J
Title:
Fission matrix methods for temperature and control feedback of small nuclear systems
Graduate Program:
Nuclear Engineering
Keywords:
Fission Matrix
Reactor Physics
Neutronics
PSBR
TRIGA
Serpent
Monte Carlo
TRACE
Breazeale
File:
Download Rau_Thesis.pdf
Committee Members:
William J Walters, Dissertation Advisor/Co-Advisor
William J Walters, Committee Chair/Co-Chair
Elia Merzari, Committee Member
Amanda M. Johnsen, Committee Member
Thomas Litzinger, Outside Member
Arthur Thompson Motta, Program Head/Chair

10. Experimental and Numerical Studies of the Droplet Sizes and Velocities near the Quench Front for Transient Reflood Conditions

open_access
Open Access
Author:
Garrett, Grant Robert
Title:
Experimental and Numerical Studies of the Droplet Sizes and Velocities near the Quench Front for Transient Reflood Conditions
Graduate Program:
Nuclear Engineering
Keywords:
Thermal Hydraulics
Core Reflood
TRACE
Nuclear Reactor Safety Analysis
Entrained Droplet Size Measurements
Entrained Droplet Velocity Measurements
Two-Phase Thermal Non-Equilibrium
Post-CHF Flow
File:
Download Grant_Garrett_PhD_Dissertation_November_11.pdf
Committee Members:
Justin Watson, Major Field Member
Robert Kunz, Outside Field Member
Fan-Bill Cheung, Chair & Dissertation Advisor
Elia Merzari, Outside Unit Member
Stphen Bajorek, Special Member
Asok Ray, Major Field Member
Arthur Thompson Motta, Program Head/Chair