Index Catalog // ScholarsArchive@OSU

The Development of a Hybrid Particle-in-Cell Simulation Code in C++ for the Modeling of the SPT-70 Hall Thruster

Creator:: Myers, Conner J.
Abstract:: In order to support the growing satellite propulsion industry, a hybrid Particle-In-Cell (PIC) simulation with fluid treatment of electrons and neutral particles was developed to model the SPT-70 Hall thruster. The 2D, C++ code assumes azimuthal symmetry and a uniform magnetic field in the radial direction with the simulation domain...
Resource Type:: Masters Thesis

CFD analysis of pressure differentials in a plate-type fuel assembly

Creator:: Roth, Gable D.
Abstract:: The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State University to evaluate fluid flow through plate-type fuel assemblies. The first plate assembly that will be examined in the facility is the Generic Test Plate Assembly (GTPA). The GTPA consists of an array of six parallel flat plates,...
Resource Type:: Masters Thesis
Full Text:: ............................................................................ 23 3.2: Line probes in the x-y plane

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

A comparison of three coarse-mesh nodal methods for boiling water reactor analysis

Creator:: Cho, Byung-Oh
Abstract:: Computer codes for versions of STORM, capable of calculating power distributions in a three-dimensional quarter-core of a boiling water reactor, were developed by using both a modified one-group and two-group diffusion theory model with several different power calculation schemes. Several numerical examples that demonstrate the high efficiency of the coarse-mesh...
Resource Type:: Masters Thesis
Full Text:: Description in Page 2.1 X-Y-Z Geometry 5 2.2 Boundary Condition Representation 9 2.3 Boundary Node

Performance of hybrid methods for representative nonproliferationproblems

Creator:: Bevill, Aaron M.
Abstract:: Adjoint-derived weight windowing is a hybrid deterministic/Monte Carlo method to simulate radiation transport. In adjoint-derived weight windowing, a deterministic adjoint solution is used to create weight windows for a Monte Carlo simulation. The intent of this work is to identify factors that reduce the Figure of Merit (FOM) of Monte...
Resource Type:: Masters Thesis
Full Text:: and y overlayed on a schematic showing the detector location in Test Case II. . . . . . 41 11 In the

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:: x direction ĵ y direction k̂ z direction µ Dynamic Viscosity (kg/m· s) µi Phase Dynamic

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

Creator:: Alberti, Anthony L.
Abstract:: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
Resource Type:: Masters Thesis

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:: computational rectangular cell (∆x and ∆y) and the directions cosines of Ω̂, the length, s, can be determined

Feasibility of Enrichment Measurements with a Pixelated CdTe HEXITEC Detector: A Comparison of Methods

Creator:: Kasparek, Dustin
Abstract:: The International Atomic Energy Agency (IAEA) is responsible for verifying the mass of elemental uranium in various forms (powders, pellets, scrap) as part of safeguards inspections at nuclear fuel fabrication facilities in support of the nuclear non-proliferation treaty. Current methods require in-field dissolution chemistry, which is time consuming and imposes...
Resource Type:: Masters Thesis
Full Text:: energy calibration equation y = ax2+mx+c which converts channels (x) into energy (y). Each pixel has its

COBRA-OSU : a fast running computer code for coupled kinetic-thermal hydraulic analysis of nuclear reactor cores

Creator:: Kaya, Sadi
Abstract:: COBRA-OSU computer code is a fast running computer code for coupled Kinetic-Thermal Hydraulic Analysis of nuclear reactor cores. This code which is based on the standard version of COBRA-IV[superscript (3)] has two major improved features. First, the COBRA-OSU computer code uses Gaussian elimination method instead of Gauss-Siedel iteration for crossflow...
Resource Type:: Masters Thesis
Full Text:: integral governing equations for these quantities are written as: cl V +f (101)dA = oat y A aafreclit

Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

Creator:: Harter, Jackson R.
Abstract:: The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF) formulation is applied to simulate phonon transport. The neutron transport code Rattlesnake is leveraged in this fashion, slightly modi ed to accept input from variables consistent with phonon transport simulations. Several benchmark problems are modeled to assess the potential...
Resource Type:: Masters Thesis
Full Text:: . . . . . . . . . . . . . . . . . . . . . . . . . . 59 21 Heat flux, y-direction . . . . . . . . . . . . . . . . . . . . . . . . . . 59 LIST OF

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

Creator:: Hallee, Brian Todd
Abstract:: The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling,...
Resource Type:: Masters Thesis
Full Text:: to determine the number of sim- ulations required to reach the prescribed criterion for knowledge

Numerical analysis of condensation induced water-hammer in horizontal piping systems

Creator:: Eichenberg, Thomas William
Abstract:: Condensation Induced Water-Hammer, CIWH, has been an historical problem for the nuclear power industry over the past 2 decades. It has caused damage to plant systems, and considerable anguish to plant operators. This thesis has embarked on an attempt to characterize the fluid motion, heat transfer, mixing, and stability of...
Resource Type:: Masters Thesis
Full Text:: could be predicted using a linear Kelvin-Helmholtz model. Additional papers by Y. Taitel & A.E. Dukler

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:: associated with systemic phenomenological sim ulation in nuclear power plants. While established for

External Coupling of Computational Fluid Dynamics Modeling of the Density Evolution Inside of the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) System with the Monte-Carlo Neutronics code Serpent 2

Creator:: Leingang, Cole W.
Abstract:: The testing of nuclear fuel under reactivity-initiated accident (RIA) conditions is paramount for the better understanding of the fuel’s behavior during these transient accident events. The Transient Reactor Test (TREAT) facility is a nuclear reactor that will be capable of recreating the thermal-hydraulic and neutronic boundary conditions representative of RIA...
Resource Type:: Masters Thesis

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:: unknowns (x,y,z velocity compenents and nine stresses.) The total number of equations that are known

The contribution of fission product decay energy uncertainty to uncertainty in calculated reactor decay power

Creator:: Baker, Steven M.
Abstract:: The uncertainty in decay energy for those fission products which contribute significantly to reactor shutdown power was evaluated. The methodology used assigned significantly larger uncertainties for data which were theoretically predicted than it did for experimentally determined data. The uncertainty was modeled as an increasing function of distance from beta...
Resource Type:: Masters Thesis
Full Text:: ) becomes a sim- ple and well defined mathematical problem: the calculation becomes a function of several

Modeling of interferences in gamma ray pulse height distributions

Creator:: Harris, Richard D. (Richard Donald), 1961-
Abstract:: The purpose of this study was to develop a model to calculate gamma ray pulse height distributions that closely approximate measured ones. The model was used to produce a pulse height distribution for a postaccident coolant sample from a nuclear reactor. Lower limits of detection were calculated for certain key...
Resource Type:: Masters Thesis
Full Text:: in the coolant. (This formula is shown in Equation 1.1.(1,8)) n {4(0) Ei(Y))Ai i ' E n X A. i

A review of experiments pertinent to the after-heat measurements of the thermal-neutron fission of U²³⁵

Creator:: Wei, Peter
Abstract:: A recent review of nuclear reactor emergency core cooling systems has required renewed investigations into the present knowledge of experiments which have measured after-heat. Of special interest are some experiments which were performed after Shure's 1961 evaluation, upon which the American Nuclear Society (ANS) recommended after-heat curves are based. Experiments...
Resource Type:: Masters Thesis
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A simulated two-group method for computing boiling water reactor power distributions

Creator:: Hatteberg, Ronald Leonard
Abstract:: A computer code capable of modeling the burnup dependent static behavior of a boiling water reactor was developed. The code calculates three-dimensional quarter core power distributions using a simulated two-group diffusion theory model. Thermal-hydraulic calculations account for the interaction between power, coolant flow, and void fraction distributions. Cross sections are...
Resource Type:: Masters Thesis
Full Text:: boundary is sim- ply 12 J Figure 2.2 Schematic of Three-Dimensional Node Geometry. S I 4Boundary

Real-time neutron radiography

Creator:: Newell, Daniel L.
Abstract:: A real-time neutron radiography system has been developed at Oregon State University which is capable of producing neutron radiographs of objects and events concurrent with the incident radiation. The purpose of this thesis is to demonstrate the feasibility of the real-time technique as a further application of neutron radiography at...
Resource Type:: Masters Thesis
Full Text:: ic03 (3 -11 D <'Ora COO CL ro 00o g CD 0 O. 0 in in , 0 c 0 c Mo 0 0 0 0O. y CL 0 r o03 r 0 3 g r 0

Extending the discrete maximum principle for the IMC equations

Creator:: Talbot, Paul W.
Abstract:: The implicit Monte Carlo (IMC) method [16] for radiative transfer, developed in 1971, provides numerical solutions to the tightly-coupled, highly-nonlinear radiative heat transfer equations in many physical situations. Despite its popularity, there are instances of overheating in the solution for particular choices of time steps and spatial grid sizes. To...
Resource Type:: Masters Thesis

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
Full Text:: evaluation that have been used for sim- ilar investigations are discussed and methods used in this thesis

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

Creator:: Strohecker, Mark F.
Abstract:: The OSU/APEX thermal hydraulic test facility models the passive safety systems of the Westinghouse AP600 advanced light water reactor design. Numerous experiments have been performed to test these systems, the one of focus here is the station blackout scenario. This experiment simulated the complete loss of AC power to all...
Resource Type:: Masters Thesis

Risk-Informed Performance-Based Methods for Cyber-Attack on Nuclear Power Facilities

Creator:: Gisondi, Andrew
Abstract:: A new approach is described that offers a risk-informed performance-based (RIPB) framework for quantifying the risk associated with a cyber-attack on a nuclear power generating facility. The first part of the method involves 1) the creation of a simplified 10 CFR 73.54 compliant cyber infrastructure, 2) modeling of design basis...
Resource Type:: Masters Thesis

Feasibility of GOTHIC for a Pressurized Conduction Cooldown Event in the High Temperature Test Facility

Creator:: Brawley, Luke P.
Abstract:: The purpose of this work was to explore the feasibility of using the GOTHIC thermal hydraulics software package to model a pressurized conduction cooldown event in the High Temperature Test Facility. To achieve that aim, a model of the facility was constructed in the GOTHIC software and a selection of...
Resource Type:: Masters Thesis

Preliminary design and analysis of a rotating bubble membrane radiator for space-based nuclear power systems

Creator:: Webb, Brent Jonathan
Abstract:: The development of a novel high temperature space radiator is described. A Rotating Bubble Membrane Radiator (RBMR) combines the best features of heat pipes and droplet radiators while avoiding their negative attributes. The RBMR offers light weight, self deployment, ease of startup and its performance is less affected by acceleration....
Resource Type:: Masters Thesis

Validation of a Transient Coupled CFD-Reactor Physics Model: An Experimental Methodology to Quantify the Accuracy of CONSTELATION for the HENRI System

Creator:: Warren, Austin M.
Abstract:: The HENRI system was developed to narrow the pulse width of TREAT from 89 ms to below 60 ms with the goal of improving the test reactor's ability to simulate RIAs in LWRs by rapidly injecting helium-3, a strong neutron poison, into the core. A coupled model using the CFD...
Resource Type:: Masters Thesis

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Creator:: Weiss, Aaron W.
Abstract:: A large, multi-year experimental program has been conducted to develop a strain gaging program for application to the flow testing of prototypic, plate-type fuel for high performance research reactors. This test program has resulted in the selection of appropriate strain gage construction, adhesives, and protective coatings to allow the acquisition...
Resource Type:: Masters Thesis
Full Text:: STRAIN GAUGE Filed March 14, 1959 2 I Y E N R O T . T A 28) \ L14 Figure 2.1: Huggenberger

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

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