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Thermal Kinetics Of Ion Irradiation Hardening In Selected Alloys For The Canadian Gen. Iv Nuclear Reactor Concept, Heygaan Rajakumar 2015 The University of Western Ontario

Thermal Kinetics Of Ion Irradiation Hardening In Selected Alloys For The Canadian Gen. Iv Nuclear Reactor Concept, Heygaan Rajakumar

Electronic Thesis and Dissertation Repository

Canada is designing supercritical water fission reactors (SCWR) to increase the thermal efficiency of nuclear power generation from ~34% to ~48%. The temperature and pressure of a supercritical water reactor core is very high compared to a CANDU reactor. This thesis examines irradiation hardening and thermal recovery of two candidate alloys, AISI 310 and Inconel 800H, for the Canadian SCWR.

Samples of both alloys are mechanically ground and polished, then irradiated using 8.0 MeV Fe ions. The use of ion irradiation safely and quickly simulates neutron damage. The change in the hardness of the samples is then studied during ...


Design And Fabrication Of Liquid Scintillator Counter, Andrea Calderon Saucedo, John L. Orrell 2015 California State University - Long Beach

Design And Fabrication Of Liquid Scintillator Counter, Andrea Calderon Saucedo, John L. Orrell

STAR (STEM Teacher and Researcher) Program Posters

Pacific Northwest National Laboratory (PNNL) is currently developing an ultra-low background liquid scintillator counter (ULB LSC) in the shallow underground laboratory. At a depth of 35-meters water-equivalent, the underground laboratory has a multi-layered shielding to keep out cosmic-ray induced background. The ULB LSC, which is located in a clean room facility, is a multi-layered design made up of various materials, including plastic scintillator veto panels, borated polyethylene, lead and copper. These layers help lower the contributions of the terrestrial background and intrinsic background, resulting from the impurities present in the materials, to the overall background count rate observed by the ...


Ion Irradiation Induced Damage And Dynamic Recovery In Single Crystal Silicon Carbide And Strontium Titanate, Haizhou Xue 2015 University of Tennessee - Knoxville

Ion Irradiation Induced Damage And Dynamic Recovery In Single Crystal Silicon Carbide And Strontium Titanate, Haizhou Xue

Doctoral Dissertations

The objective of this thesis work is to gain better understanding of ion-solid interaction in the energy regime where electronic and nuclear energy loss are comparable. Such responses of materials to ion irradiations are of fundamental importance for micro-electronics and nuclear applications. The ion irradiation induced modification for the crystal structure, the physical and chemical properties etc. may strongly affect the performance of functional materials that needs to be better understood.

Experimentally, ion irradiation induced damage accumulation and dynamic recovery in SiC [silicon carbide] and SrTiO3 [strontium titanate] were studied in this dissertation project. Five chapters are presented: Firstly ...


Requirements For A Computer Code System For The Development And Maintenance Of Target Sets, Christopher Chwasz 2015 University of Tennessee - Knoxville

Requirements For A Computer Code System For The Development And Maintenance Of Target Sets, Christopher Chwasz

Masters Theses

In the field of commercial nuclear reactor security, the concept of target sets has matured since its invention in the late 1980s and early 1990s to the codification of target set regulations by the United States Nuclear Regulatory Commission in 2009 and publishing of official guidance in 2010. Target sets have evolved into a complex and useful tool to develop and test a protective strategy. By their definition, target sets are the “minimum combination of equipment or operator actions which, if all are prevented from performing their intended safety function or prevented from being accomplished, would likely result in significant ...


Sensitivity Analysis Of Fuel Cladding Temperature To Dry Cask Loading And Storage Conditions, Remy Russell DeVoe 2015 University of Tennessee - Knoxville

Sensitivity Analysis Of Fuel Cladding Temperature To Dry Cask Loading And Storage Conditions, Remy Russell Devoe

Masters Theses

Dry cask safety analyses and material degradation studies depend on reliable best- estimate thermal models. Gaps in design data and storage site conditions require analysts to frequently rely on bounding assumptions in thermal models that introduce bias to the results. Efforts to gather physical attributes of cask designs from vendors or experimental measurements can be costly and to determine all the uncertain parameters for a number of different cask designs is impractical. Measuring the sensitivity of peak cladding temperature to cask and fuel depletion modeling parameters was done to inform decision makers of which parameters that have the most impact ...


The Nuclear Security Science And Policy Institute At Texas A&M University, Claudio A. Gariazzo, Kelley H. Ragusa, David R. Boyle, William S. Charlton, Sunil S. Chirayath, Craig M. Marianno, Paul Nelson Jr. 2015 Texas A&M University

The Nuclear Security Science And Policy Institute At Texas A&M University, Claudio A. Gariazzo, Kelley H. Ragusa, David R. Boyle, William S. Charlton, Sunil S. Chirayath, Craig M. Marianno, Paul Nelson Jr.

International Journal of Nuclear Security

The Nuclear Security Science and Policy Institute (NSSPI) is a multidisciplinary organization at Texas A&M University and was the first U.S. academic institution focused on technical graduate education, research, and service related to the safeguarding of nuclear materials and the reduction of nuclear threats. NSSPI employs science, engineering, and policy expertise to: (1) conduct research and development to help detect, prevent, and reverse nuclear and radiological proliferation and guard against nuclear terrorism; (2) educate the next generation of nuclear security and nuclear nonproliferation leaders; (3) analyze the interrelationships between policy and technology in the field of nuclear security; and (4) serve as a public resource for knowledge and skills to reduce nuclear threats. Since 2006, over 31 Doctoral and 73 Master degrees were awarded through NSSPI-sponsored research. Forty-one of those degrees are Master of Science in Nuclear Engineering with a specialization in Nuclear Nonproliferation and 16 were Doctorate of Philosophy degrees with a specific focus on nuclear ...


Addressing Imbalances In Us Nuclear Economic And Nonproliferation Policies, Matthew S. Duchene, Howard Hall 2015 Institute for Nuclear Security

Addressing Imbalances In Us Nuclear Economic And Nonproliferation Policies, Matthew S. Duchene, Howard Hall

International Journal of Nuclear Security

Foreign civilian nuclear start-ups have an increasing number of international partners capable of supplying fuel cycle technologies. The desire to prevent the spread of dual-use enrichment and reprocessing technology by asking partner states to rely on international fuel markets is a major obstacle for US negotiating civilian nuclear trade agreements, leading to delays. US participation in emerging nuclear markets is being undercut by foreign competition, leading to decreasing economic competition and influence in international nonproliferation issues. It is therefore necessary for the US to reinvest and complete its domestic nuclear fuel cycle and modify its process for implementing civilian nuclear ...


Radiation Damage As A Possible Metal Chronometer For Pre-Detonation Nuclear Forensics, Edward T. Peskie, Howard L. Hall 2015 United States Military Academy

Radiation Damage As A Possible Metal Chronometer For Pre-Detonation Nuclear Forensics, Edward T. Peskie, Howard L. Hall

International Journal of Nuclear Security

The ability to determine the time since the forming of seized nuclear material would provide crucial data to be used in its investigation. This paper examines the effects of radiolytic damage caused by the decay of uranium isotopes and assesses the potential forensic utility of examination of these damage regions for determining the time since forming of a metal sample. This paper draws parallels from studies of fission track dating in mineral samples under geologic time and proposes modifications to previously published work in the field of α-recoil track dating in order to determine the time since a metal sample ...


Impurity Diffusion As A Possible Metal Chronometer For Pre-Detonation Nuclear Forensics, Edward T. Peskie, Howard L. Hall 2015 United States Military Academy

Impurity Diffusion As A Possible Metal Chronometer For Pre-Detonation Nuclear Forensics, Edward T. Peskie, Howard L. Hall

International Journal of Nuclear Security

The ability to determine the time since forming of seized nuclear material would provide crucial data to be used in its investigation. The time dependent processes of diffusion relevant to this need are examined; to include grain boundary diffusion, and discontinuous precipitation, and an assessment is performed of the utility of examination of impurity and alloying element concentration profiles for use as a pre-detonation nuclear forensics tool for determining the age of a metal sample. Several examples illustrate the effects of time on both binary alloys and multi-component systems. Parallels are drawn from studies of diffusion in mineral samples under ...


Masthead, 2015 University of Tennessee, Knoxville

Masthead

International Journal of Nuclear Security

No abstract provided.


Cover, 2015 University of Tennessee, Knoxville

Cover

International Journal of Nuclear Security

No abstract provided.


From The Editor, 2015 University of Tennessee, Knoxville

From The Editor

International Journal of Nuclear Security

No abstract provided.


Student Writing Competition, 2015 University of Tennessee, Knoxville

Student Writing Competition

International Journal of Nuclear Security

No abstract provided.


Electronic Energy Loss Of Heavy Ions And Its Effects In Ceramics, Ke Jin 2015 University of Tennessee - Knoxville

Electronic Energy Loss Of Heavy Ions And Its Effects In Ceramics, Ke Jin

Doctoral Dissertations

Energy loss of medium energy heavy ions (i.e. Cl, Br, I, and Au) in thin compound foils containing light elements (i.e. silicon carbide and silicon dioxide) is directly measured using a time-of-flight elastic recoil detection analysis (ToF-ERDA) technique. An improved data analysis procedure is proposed to provide the experimentally determined electronic stopping powers. This analysis procedure requires reliable predictions of nuclear stopping. Thus, the nuclear stopping predicted by the Stopping and Range of Ions in Matter (SRIM) code is validated by measuring the angular distribution of 1 MeV Au ions after penetrating a thin silicon nitride foil, using ...


User Perspective And Analysis Of The Continuous-Energy Sensitivity Methods In Scale 6.2 Using Tsunami-3d, Elizabeth Lauryn Jones 2015 University of Tennessee - Knoxville

User Perspective And Analysis Of The Continuous-Energy Sensitivity Methods In Scale 6.2 Using Tsunami-3d, Elizabeth Lauryn Jones

Masters Theses

The Tools for Sensitivity and UNcertainty Analysis Methodology Implementation (TSUNAMI) suite within the SCALE code system makes use of eigenvalue sensitivity coefficients to enable several capabilities, such as quantifying the data-induced uncertainty in calculated eigenvalues and assessing the similarity between different critical systems. The TSUNAMI-3D code is one tool within the TSUNAMI suite used to calculate eigenvalue sensitivity coefficients in three-dimensional models. The SCALE 6.1.2 code system includes only the multigroup (MG) mode for three-dimensional sensitivity analyses; however, the upcoming release of SCALE 6.2 will feature the first implementation of continuous-energy (CE) sensitivity methods in SCALE. For ...


Hybrid K-Edge Densitometry As A Method For Materials Accountancy Measurements In Pyrochemical Reprocessing, Matthew Tyler Cook 2015 University of Tennessee - Knoxville

Hybrid K-Edge Densitometry As A Method For Materials Accountancy Measurements In Pyrochemical Reprocessing, Matthew Tyler Cook

Doctoral Dissertations

Pyrochemical reprocessing is a proven method to recover useful fissile material from spent nuclear fuel. The process requires high temperatures and an inert atmosphere thus complicating the prospect of making materials accountancy measurements. Development of a measurement method for materials accountancy measurements has become necessary since pyroprocessing is receiving more attention as a possible compliment to aqueous reprocessing methods. If pyroprocessing is to be adapted from the engineering scale to a commercially viable reprocessing method a comprehensive safeguards measurement method and strategy must be developed.

Hybrid k-edge densitometry (HKED) has been applied to aqueous reprocessing measurements in commercial facilities. This ...


Modeling Radiation-Induced Segregation In Ferritic-Martensitic Steels, Aaron Patrick Selby 2015 University of Tennessee - Knoxville

Modeling Radiation-Induced Segregation In Ferritic-Martensitic Steels, Aaron Patrick Selby

Masters Theses

As ferritic-martensitic (FM) steels receive increasing interest, due to the development of Generation IV fission reactors and fusion reactors, it is imperative to understand how the metals will behave under irradiation. Of the radiation effects, radiation-induced segregation (RIS) is of particular concern as it can lead to the formation of intermetallic phases, stress corrosion cracking, and other detrimental effects. However, predicting RIS in FM steels is more complex due to the lack of consistent trends in experimental results. Therefore, we developed a program to simulate RIS in FM alloys. By performing a sensitivity analysis of the input parameters, we found ...


Assessment Of Reactivity Equivalence For Enhanced Accident Tolerant Fuels In Light Water Reactors, Nathan Michael George 2015 University of Tennessee - Knoxville

Assessment Of Reactivity Equivalence For Enhanced Accident Tolerant Fuels In Light Water Reactors, Nathan Michael George

Doctoral Dissertations

The neutronic behavior of accident tolerant fuel (ATF) concepts was simulated in light water reactors (LWRs) to establish design parameters to match reactivity lifetime requirements of standard UO2 [uranium dioxide]/Zircaloy fuel. The two concepts discussed in this dissertation are fully ceramic micro-encapsulated (FCM) fuel and alternate cladding concepts. To compare the required fuel alterations against standard UO2/Zircaloy fuel, a 2D lattice-physics based reactivity equivalence method was established to estimate excess reactivity at the completion of each weighted batch cycle.

In the case of FCM fuel, the uranium-based tristructural isotropic (TRISO) kernel and the surrounding particle layers ...


Dynamic Modeling Of A Small Modular Reactor For Control And Monitoring, Jeffrey Robert Kapernick 2015 University of Tennessee - Knoxville

Dynamic Modeling Of A Small Modular Reactor For Control And Monitoring, Jeffrey Robert Kapernick

Masters Theses

A system model of the Babcock & Wilcox Generation mPower small modular reactor (SMR) was developed within the MATLAB-Simulink environment. A detailed physical configuration of this SMR was established based on the limited information available for the mPower reactor. This is an important step in the development of the simulation model. Three mathematical models were combined to simulate the control dynamics. A lumped-parameter approximation of fuel-to-coolant heat transfer is combined with vessel upper plenum and lower plenum coolant masses to represent the core power and heat transfer dynamics. A nodalized moving boundary steam generator model balances mass, momentum, and energy for ...


Impact Of Fuel Rod Coatings On Reactor Performance And Safety, Ian Robert Stewart 2015 University of Tennessee - Knoxville

Impact Of Fuel Rod Coatings On Reactor Performance And Safety, Ian Robert Stewart

Masters Theses

This study evaluates the use of a ceramic coating on the Zr-alloy cladding within a PWR using four ceramic compounds of 5 and 10 micron thicknesses: ZrO2, TiAlN, Ti2AlC, and Ti3AlC2. The film’s impact is assessed for variation on: reactivity, fuel cycle length, maximum temperature, film’s roughness, and transient conditions. The reactivity is analyzed using the following methods: change in the multiplication factor (k) each film introduces to the system using the ABH method, and Monte Carlo software (MCNP). Both methods are in good agreement, yielding less than half a percent change from a reference, no-film fuel pin ...


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