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Start Over Graduate Program Nuclear Engineering Keyword CTF

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

2. Investigation of Coupled Code Pressurized Water Reactor Simulations Using CTF with Soluble Boron Tracking

open_access
Open Access
Author:
Biery, Mark Byron
Title:
Investigation of Coupled Code Pressurized Water Reactor Simulations Using CTF with Soluble Boron Tracking
Graduate Program:
Nuclear Engineering
Keywords:
Reactor Core
Coupled Code
NEM
CTF
Boron
Boron Tracking
Mixed Oxide
MOX
PWR
Dillution
Transient
Benchmark
File:
Download M._BIERY_MS_THESIS_-_Spring_2013.pdfDownload M._BIERY_MS_THESIS_-_Spring_2013__Rev._1_.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor

3. HIGH-FIDELITY MULTI-PHYSICS COUPLING FOR PREDICTION OF ANISOTROPIC POWER AND TEMPERATURE DISTRIBUTION IN FUEL ROD: IMPACT ON HYDRIDE DISTRIBUTION

open_access
Open Access
Author:
Davis, Ian James
Title:
HIGH-FIDELITY MULTI-PHYSICS COUPLING FOR PREDICTION OF ANISOTROPIC POWER AND TEMPERATURE DISTRIBUTION IN FUEL ROD: IMPACT ON HYDRIDE DISTRIBUTION
Graduate Program:
Nuclear Engineering
Keywords:
hydrogen distribution
hydride
BISON
DeCART
CTF
COBRA
MOOSE
clad temperature
coupling
high-fidelity
multi-physics
File:
Download davis_thesis_v2.7.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

4. Development of Burnup Dependent Fuel Rod Model in Cobra-tf

open_access
Open Access
Author:
Ozdemir Yilmaz, Mine
Title:
Development of Burnup Dependent Fuel Rod Model in Cobra-tf
Graduate Program:
Nuclear Engineering
Keywords:
COBRA-TF
CTF
FRAPCON
FRAPTRAN
subchannel
fuel performance
thermal conductivity degradation
TCD
REA
Halden
fuel centerline temperature
MATPRO
File:
Download Mine_Yilmaz_Dissertation_ETD_Version_Final.pdf
Committee Members:
Maria Nikolova Avramova, Dissertation Advisor/Co-Advisor
Maria Nikolova Avramova, Committee Chair/Co-Chair
Kostadin Nikolov Ivanov, Committee Member
Turgay Ertekin, Committee Member
Arthur Thompson Motta, Committee Member
Jens G Munthe Andersen, Special Member