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Start Over Degree MS Committee Member Maria Nikolova Avramova

1. MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA

open_access
Open Access
Author:
Nelson, Adam Gregory
Title:
MONTE CARLO METHODS FOR NEUTRON TRANSPORT ON GRAPHICS PROCESSING UNITS USING CUDA
Graduate Program:
Nuclear Engineering
Keywords:
gpu
neutron transport
gp-gpu
monte carlo
cuda
File:
Download Adam_Gregory_Nelson_Thesis_Final.pdf
Committee Members:
Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor
Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

2. 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

3. MODELING THE EFFECTS OF FUEL ROD CRUD FORMATION ON BOILING HEAT TRANSFER IN A PRESSURIZED WATER REACTOR USING EULERIAN TWO-FLUID CFD

open_access
Open Access
Author:
Guzzetta, Ashley Susan
Title:
MODELING THE EFFECTS OF FUEL ROD CRUD FORMATION ON BOILING HEAT TRANSFER IN A PRESSURIZED WATER REACTOR USING EULERIAN TWO-FLUID CFD
Graduate Program:
Nuclear Engineering
Keywords:
nuclear
pressurized water reactors
crud model
subcooled boiling
heat transfer
CFD
crud formation
File:
Download MS_Thesis_Guzzetta.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Robert Francis Kunz, Thesis Advisor/Co-Advisor

6. SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED SUBCHANNEL AND SYSTEM CODES FOR PRESSURIZED WATER REACTOR TRANSIENT APPLICATIONS

open_access
Open Access
Author:
SOLER-MARTINEZ, MARIA DESAMPARADOS
Title:
SEMI-IMPLICIT THERMAL-HYDRAULIC COUPLING OF ADVANCED SUBCHANNEL AND SYSTEM CODES FOR PRESSURIZED WATER REACTOR TRANSIENT APPLICATIONS
Graduate Program:
Nuclear Engineering
Keywords:
RELAP5/COBRA-TF
semi-implicit coupling
coupling codes
File:
Download Thesis_Soler.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

7. Data Analysis and Modeling of NESTOR SSG Heated Rod Bundle Experiments using VIPRE-I for the Assessment of the Onset of Nucleate Boiling Criteria

open_access
Open Access
Author:
Salko, Robert Keith
Title:
Data Analysis and Modeling of NESTOR SSG Heated Rod Bundle Experiments using VIPRE-I for the Assessment of the Onset of Nucleate Boiling Criteria
Graduate Program:
Nuclear Engineering
Keywords:
VIPRE
ONB
NESTOR
File:
Download SalkoMSThesis.pdf
Committee Members:
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

10. 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

11. 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

13. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel

open_access
Open Access
Author:
Shapiro, Rachel Ann
Title:
Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel
Graduate Program:
Nuclear Engineering
Keywords:
PWR
TRISO
accident-tolerant fuel
fully ceramic microencapsulated fuel
neutronics
File:
Download Final_Thesis.pdf
Committee Members:
Massimiliano Fratoni, Thesis Advisor/Co-Advisor
Arthur Thompson Motta, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor

19. Verification of Laminar and Transitional Flow Simulations in Porous Media with Nek5000

open_access
Open Access
Author:
Holler, David Michael
Title:
Verification of Laminar and Transitional Flow Simulations in Porous Media with Nek5000
Graduate Program:
Nuclear Engineering
Keywords:
verification
laminar flow
transitional flow
porous media
incompressible
Nek5000
computational fluid dynamics
CFD
open source
File:
Download David_Holler_MS_Thesis.pdf
Committee Members:
Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor
Maria Nikolova Avramova, Thesis Advisor/Co-Advisor