Index Catalog // ScholarsArchive@OSU

An Approach to Modeling Fuel Plate Deformations in Fluid-Structure Interactions

Creator:: Howard, Trevor
Abstract:: As computational power increases, so does the desire to use fluid-structure interaction (FSI) software to design complex systems and components such as fuel plates. Presently, an effort is underway to support the design and qualification of a new nuclear fuel material which is intended for applications in select, plate-type, research...
Resource Type:: Masters Thesis
Full Text:: distributed load (w) on a beam; given as 4 4 d z D w dx  , (11) where D is the flexural rigidity of

Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

Creator:: Nes, Razvan
Abstract:: An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
Resource Type:: Dissertation

On the Role of Particle Size Distribution in Selective Laser Melting of 316L Stainless Steel

Creator:: Coe, Hannah G.
Abstract:: Selective laser melting (SLM) is an additive manufacturing (AM) process that uses a laser beam to melt metal powder as it is spread onto the build surface using a roller or scraper, followed by rapid solidification to manufacture a 3D component, one layer at a time. In SLM process, density...
Resource Type:: Masters Thesis
Full Text:: Tucker, Dr. Brian Paul, and Dr. Brian Woods for your time, patience, and feedback My deepest thanks

A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

Creator:: Jackson, R. Brian
Abstract:: Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was to study core channel flow reversal susceptibility in the Gas Reactor Test Section (GRTS) at low flow conditions. The second objective was the development of...
Resource Type:: Masters Thesis
Full Text:: fly_leaf AN ABSTRACT OF THESIS OF R. Brian

On the mechanism transition of power transient critical heat flux

Creator:: Yan, Yikuan
Abstract:: The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
Resource Type:: Dissertation
Full Text:: committee members: Dr. Qiao Wu Dr. Brian Fronk, Dr. Brian Woods. and the GCR Dr. Leah Minc. I would

Numerical Investigation of Unsteady Inertial and Turbulent Flows Through Porous Media: Pore-scale DNS, Flow Analyses and Upscaling

Creator:: He, Xiaoliang
Abstract:: Porous media are the materials containing void space or pores, where fluids and gases can pass through. Unsteady flows in porous media are encountered in many engineering applications and natural problems, such as CO₂ sequestration, high temperature nuclear reactor cooling, high efficiency combustion, chemical reactors, noise reduction on airplane trailing...
Resource Type:: Dissertation
Full Text:: me to the right path. I would like to thank Dr. James Liburdy, Dr. Deborah Pence, Dr. Brian Wood

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

Creator:: Jensen, Philip
Abstract:: The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypical plate type fuel. OSU's fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI's...
Resource Type:: Masters Thesis
Full Text:: direction [13]. 11 Of these modifications the work of Smith, has been employed in the nuclear

A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

Creator:: Winkle, Tristan
Abstract:: Vibration of nuclear fuel rods is an area of significance for the long-term safe operation of any nuclear power plant. One mechanism of vibration, flow induced vibration (FIV), must be quantified when designing a new core, such as a sodium fast reactor which employs helically-wrapped wire spacers. Experimental work undertaken...
Resource Type:: Masters Thesis
Full Text:: r w ww t N D f F D F S  +  = +    (2.6) where Re is the Reynolds number, rN is the

Heat Transfer Coefficient Correlation Development of Dowtherm A in the Near Wall Region of a Pebble Bed Reactor

Creator:: Dionne, Connor J.
Abstract:: Computational fluid dynamics conjugate heat transfer simulations were performed on a packed bed test facility using Dowtherm-A as the working fluid. Multiple test cases were simulated for a Reynolds number range of 188 – 1524 and a set heater power of 60 kW. Temperature profiles were extracted, and the near-wall...
Resource Type:: Masters Thesis
Full Text:: support, tips, and workarounds to my problems. I would also like to thank Dr. Brian Jackson from Kairos

Top-down scaling analysis of the integral reactor vessel test facility

Creator:: Graves, Joshua D.
Abstract:: Oregon State University has conducted research in collaboration with TerraPower, LLC, to perform a top-down scaling analysis of an integrated test facility. The goal of this facility is to simulate transient and quasi-steady phenomena at a reduced scale, including steady-state operation, pump coastdown, natural circulation, reactor head heat transfer, and...
Resource Type:: Masters Thesis
Full Text:: - Grashof number g - Gravitational acceleration [m 2 ]s H - Convective heat transfer coefficient W

Quantification of dry concentration factor for Cs-134 in marine diatom Thalassiosira Weissflogii

Creator:: Krzyaniak, Nathan Anthony
Abstract:: The Fukushima Daiichi nuclear disaster of 2011 made it apparent that releases of fission products to marine environments is a very real possibility. Additional data on the movement of material through marine environments can be used by radioecology personnel to assist with both ecosystem protection as well as environmental cleanup...
Resource Type:: Masters Thesis

Development of a Rapid Power Transient Critical Heat Flux Model

Creator:: Brown, Emory G.
Abstract:: The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
Resource Type:: Dissertation
Full Text:: abilities as a young researcher. I would also like to thank my committee members, Dr. Brian Woods, Dr

Numerical study of droplet formation with nozzle dynamics and multiple droplet impingement

Creator:: Sangplung, Saangrut
Abstract:: Droplet formation from a flexible nozzle plate driven by a prescribed-waveform excitation of a piezoelectric is numerically investigated using a computational fluid dynamics (CFD) model with the VOF method. The droplet generator with a flexible nozzle plate, which is free to vibrate due to the pressure acting on the plate,...
Resource Type:: Dissertation
Full Text:: = Nondimensional contact line velocity, UCL / U0 u,v,w = Velocity components uc = Capillary velocity UCL

Reduced Order Modeling of Radiation Diffusion Kinetics via Proper Generalized Decomposition

Creator:: Alberti, Anthony L.
Abstract:: In this dissertation, we attempt to overcome the "curse of dimensionality" inherent to radiation diffusion kinetics problems by employing a novel reduced order modeling technique known as proper generalized decomposition (PGD). After verifying a proposed PGD algorithm and associated solvers through various tests, we explore its performance for computing reduced-order...
Resource Type:: Dissertation

Radiative heat transfer in combustion applications : parallel efficiencies of two gas models, turbulent radiation interactions in particulate laden flows, and coarse mesh finite difference acceleration for improved temporal accuracy

Creator:: Cleveland, Mathew A.
Abstract:: We investigate several aspects of the numerical solution of the radiative transfer equation in the context of coal combustion: the parallel efficiency of two commonly used opacity models, the sensitivity of turbulent radiation interaction (TRI) effects to the presence of coal particulate, and an improvement of the order of temporal...
Resource Type:: Dissertation

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

Creator:: Riley, Thomas H.
Abstract:: The goal of this project was to pave the way for more data-driven decision making when considering safety within Nuclear Engineering by proving the concept of new and innovative accident scenario modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple, if extremely...
Resource Type:: Dissertation
Full Text:: . Thank you to my committee: Dr. Brian Woods; Dr. Wade Marcum; Dr. Todd Palmer; and Dr. Albert Stetz

Experimental Study of the Impact of Physical and Chemical Properties on Smoldering Combustion in Natural Fuels

Creator:: Smucker, Benjamin
Abstract:: Smoldering combustion in wildland fires is difficult to extinguish, can transition to flaming combustion, and produces a significant amount of pollutants. It is necessary to understand parameters controlling smoldering in order to help predict the smoldering behavior and potentially mitigate these hazards. The wide variety of natural fuels that occur...
Resource Type:: Dissertation

Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems

Creator:: Somasundaram, Elanchezhian
Abstract:: The implementation of advanced hybrid (Monte Carlo/Deterministic) transport methods for realistic test problems has been a challenge due to the overhead efforts associated with interfacing a solution generated by a deterministic solver with a Monte Carlo based radiation transport code. In this work, with the help of Transpire, Inc., a...
Resource Type:: Dissertation
Full Text:: . Brian Woods, professor Dr. Leah Minc and my minor professor, Dr. Lisa J. Madsen for serving as my

Effects of fluid axial conduction on liquid metal natural circulation and linear stability

Creator:: Sabharwall, Piyush
Abstract:: The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through non-dimensional analysis, steady-state assessment, and linear perturbation evaluation. The Nyquist criterion and a root search method were employed to find the linear stability boundary of both forward and backward circulations....
Resource Type:: Masters Thesis
Full Text:: also like to thank the other members of my committee, Dr. Brian Woods, Dr. Richard Peterson and Dr

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

Creator:: Thody, Austin
Abstract:: Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
Resource Type:: Masters Thesis
Full Text:: (Dr. Brian Woods, Dr. Leah Minc, Dr. Andrew Klein and Dr. Wade Marcum) for their help. I would

Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

Creator:: Wuth, Bradyn J.
Abstract:: Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to model the Korean Atomic Energy Research Institute's SMART reactor, the Žukauskas...
Resource Type:: Masters Thesis

Phase distribution parameter determination by neutron radiography

Creator:: Skinner, Jesse B.
Abstract:: A phase distribution parameter has been added to the one-dimensional two-phase horizontal flow conservation equations. The phase distribution parameter was incorporated into the conservation equations in an attempt to add stability and remove correlation switching by incorporating gravity. Determination of the phase distribution parameter requires an average void fraction profile...
Resource Type:: Masters Thesis
Full Text:: ; song & Ishii, 2001). ( ) 2 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 cos 14 v t w w i i i v C

Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

Creator:: Peguero, Lara M.
Abstract:: Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research reactor currently utilizing IRT-4M fuel made by a single Russian supplier. A candidate for...
Resource Type:: Masters Thesis

Design of a Pebble Bed Separate Effects Test for Molten Salt Reactors

Creator:: Uselman, Jacob S.
Abstract:: The licensing of novel nuclear reactor power plant designs requires extensive research and testing. A significant portion of this work is dedicated to the design and operation of scaled-down testing facilities that emulate various plant conditions. The data gathered from these test facilities is used to compare to predictive models....
Resource Type:: Masters Thesis
Full Text:: . Finally, the author would like to thank Dr. Brian Woods, for teaching the importance of safety and

Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

Creator:: Deason, Wesley
Abstract:: Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise...
Resource Type:: Masters Thesis

Binary stochastic media transport : a coupled mesh based method

Creator:: Barnett, Nathan A.
Abstract:: Transport in a binary stochastic media has been an area of interest for many applications over the past three decades. Many different methods have been attempted, most based on the Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve problems where a large amount of...
Resource Type:: Masters Thesis

Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

Creator:: Keller, S. Todd
Abstract:: Attila is a state-of-the-art radiation transport based code that is efficient, accurate and straightforward to use. Geometric information is input to the code as CAD drawings. Material property information is input as a cross section library. The user has full control over standard transport options and output reports. In phase...
Resource Type:: Masters Thesis
Full Text:: possible. Thanks as well to my committee members, Dr. Brian Woods of the Nuclear Engineering and

Effects of a thin, flexible nozzle on droplet formation and impingement

Creator:: Hawke, Shane R.
Abstract:: The droplet formation process in the vicinity of the nozzle exit and the behavior of a spreading droplet during impingement on a smooth glass surface were studied. Two nozzle geometries were tested. The first case was a stiff stainless steel nozzle plate 0.787 mm thick. The second case was a...
Resource Type:: Masters Thesis
Full Text:: . Brian Woods for serving on his graduate committee. Finally, the author would like to thank Jian

Adaptive methods for robust commercial vehicle control

Creator:: Junell, Jaime L.
Abstract:: This thesis explores the implementation of learning based control with predictive cruise control and the potential this technology has for increasing fuel efficiency while keeping on a well maintained schedule for commercial trucks. Traditional cruise control is wasteful when maintaining a constant velocity over rolling hills. Predictive cruise control is...
Resource Type:: Masters Thesis
Full Text:: , then the v is a n×m matrix and w is a j× k matrix. There are also bias weights for each hidden unit

Heat Loss Characterization of NIST-1's Containment Vessel

Creator:: Yoshiura, Ramon K.
Abstract:: NuScale Power has designed a small modular reactor using natural circulation cooling dependent systems for both steady-state and transient operations. The NuScale Integral Test System (NIST-1) facility was built to supply test data to NuScale Power to verify and validate computer codes for the NuScale Power Mod- ule (NPM) with...
Resource Type:: Masters Thesis
Full Text:: + for the solid volume . 24 3.3 Approximate Values of the Heat Transfer Coefficient h, W/(m2K) . 28

Predicting antineutrino source terms from a high temperature gas reactor

Creator:: Shaughnessy, Andra L.
Abstract:: Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors and are able to determine power levels and burn up throughout a fuel cycle. This technology could allow the IAEA to monitor LWRs remotely and...
Resource Type:: Masters Thesis
Full Text:: Brian: I would not have made it through all those classes without your hours of explanation. Thanks so

Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

Creator:: Abel, Kent C.
Abstract:: The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for these calculations is known as the two-fluid model. It is the most accurate of the two-phase models since it considers each phase independently and links...
Resource Type:: Dissertation
Full Text:: V. Pence, Dr. Brian Woods and Dr. Vinod Narayanan, for their valuable comments and their time. I

Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

Creator:: Danielson, Jordan J.
Abstract:: All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing instruments are differential pressure sensing meters, which are invasive and could be the failure source in the pressure boundary of the primary coolant system. In...
Resource Type:: Masters Thesis

Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

Creator:: Higgins, Anton
Abstract:: The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
Resource Type:: Masters Thesis

Extending the applicability of implicit Monte Carlo Diffusion : frequency dependence and variance reduction using the difference formulation

Creator:: Cleveland, Mathew A.
Abstract:: The intent of this work is to extend Implicit Monte Carlo Diffusion (IMD)[Gen. 2001] to account for frequency dependence and to incorporate the difference formulation[Szo. 2005] as a source manipulation variance reduction technique. This work shows the derivation of the probabilities and the associated proofs which govern the frequency dependent...
Resource Type:: Masters Thesis
Full Text:: ; Dr. Brian Woods, Dr. Sourabh Apte, and Dr. Ken Krane, for their time and commitment to my thesis

Hydrodynamics of droplet impingement on heated surfaces : effects of nanofluid and nano-structured surface

Creator:: Shen, Jian
Abstract:: This study investigates the hydrodynamic characteristics of droplet impinging on heated surfaces using High Speed High Resolution (HSHR) imaging and evaluates the effect of surface temperature and using water and a nanofluid on a polished and a nano-structured surface. Three types of surfaces are used in the study: polished silicon,...
Resource Type:: Dissertation
Full Text:: Douglas Heymann for his help and inspiration in MATLAB image processing. Thanks also to Dr. Brian

The Development of a Mechanistic Critical Heat Flux Correlation

Creator:: Luitjens, Jeffrey M.
Abstract:: A mechanistic based critical heat flux (CHF) correlation has been developed derived from a mass, momentum, and energy balance at a nucleation site for water. The trigger mechanism for the CHF condition is postulated to be related to the maximum boiling frequency on a heated surface. It is observed that...
Resource Type:: Dissertation
Full Text:: density σ surface tension τw wall shear stress θ contact angle θa advancing contact angle θd dynamic

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Creator:: Goodrich, Sam S.
Abstract:: In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
Resource Type:: Dissertation

Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

Creator:: Lam, Adam Q.
Abstract:: In this dissertation, we derive and implement a new transport-diffusion hybrid algorithm for solving thermal radiative transfer (TRT) problems. Using the method of nonlinear elimination (NLEM), the TRT system of equations can be written in terms of a transport equation with the absence of scattering and a diffusion equation. The...
Resource Type:: Dissertation
Full Text:: as w = s∫ 0 ds′ w0 exp{(−σs′)} = 1 σ w0 [1− exp{(−σs)}] . (3.35) The location at which a

Site specific reference person parameters and derived concentration standards for the Savannah River site

Creator:: Stone, Daniel K.
Abstract:: The U.S. Department of Energy (DOE) Order 458.1 states that the compliance with the DOE annual dose limit of 1 mSv (100 mrem) to a member of the public may be demonstrated by calculating dose to the maximally exposed individual (MEI) or to a representative person. Historically, the MEI concept...
Resource Type:: Masters Thesis
Full Text:: multiplied by the radiation factor for each radionuclide, seen in eqn 2. 6 𝐻! = 𝑤

Effect of PZT driving waveform and frequency on meniscus shape and dropon-demand droplet formation parameters

Creator:: Yang, Guozhong
Abstract:: For piezoelectric stack (PZT) driven droplet generator, the driving waveform and driving frequency effect on liquid filament shape and droplet characteristics have been experimentally studied. The experimental study was based on a PZT driven droplet generator with known geometric design parameters and working fluid properties. A lumped-element-model (LEM) constructed to...
Resource Type:: Dissertation
Full Text:: u aρ µ ⋅ ⋅ = Stokes number; ν ω 2a St ⋅ = Volume Weber number; e a W ρ γ

Pressure losses across a 180 degree turn in the AP1000 cooling annulus

Creator:: Nelson, Roy K.
Abstract:: A one-sixth scaled facility was constructed at Oregon State University to determine the pressure losses around Westinghouse's AP1000 Passive Containment Cooling System. An explanation of the AP1000 Passive Containment Cooling System is given. This study examined the pressure loss and loss coefficient around the 180 degree turn of the Passive...
Resource Type:: Masters Thesis
Full Text:: corrections. I would like to give thanks to Brian Jackson and Wade Marcum for their advice and suggestions

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Creator:: Reynolds, Aaron J.
Abstract:: Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor (DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other reactor types. This environment can be computationally challenging to model, given that the multiphysics phenomena generally have non-linear interdependencies requiring the use of iterative solution...
Resource Type:: Dissertation

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

Creator:: Misner, Alex C.
Abstract:: Antineutrino detectors could provide a valuable addition to current safeguards regimes. Antineutrinos are an attractive emission to monitor due to their low interaction cross-section that prevents them from being shielded and the dependence of their spectrum on the power level and isotopic content of a reactor core. While there are...
Resource Type:: Dissertation

Quantified PIRT and uncertainty quantification for computer code validation

Creator:: Luo, Hu
Abstract:: This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
Resource Type:: Dissertation
Full Text:: help from graduate students Jeffrey Luitjens and Brian Halle on RELAP data processing and testing

Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

Creator:: Hummel, Andrew J.
Abstract:: The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be...
Resource Type:: Dissertation
Full Text:: their time and friendship. Jarvis Caffrey, Brian Gullekson, Kevin Makinson, Robert Schikler, and

Feasibility study on a soluble boron-free small modular reactor

Creator:: Mart, Justin R.
Abstract:: The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
Resource Type:: Masters Thesis
Full Text:: Figure 20: kinf vs burnup for BP geometry 1 and 3, with 12% and 2% w/o Gd2O3. ................. 64

On Primary Vortex Shedding Regimes between Long Tandem Plates

Creator:: Howard, Trevor Kent
Abstract:: Vortex shedding is a phenomenon relevant to any industry dealing with fluid flow. The shed vortices often produce oscillatory forces, which have been suspect in the catastrophic failure of airplanes and bridges alike. To prevent further engineering failures a better understanding of the underlying physics is needed. It has been...
Resource Type:: Dissertation

Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

Creator:: Yoshiura, Ramon K.
Abstract:: The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
Resource Type:: Dissertation

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