You searched for +publisher:"The Ohio State University" +contributor:("Blue, Thomas"). Showing records 1 – 29 of 29 total matches.
1. Hawn, David Phillip. Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink.
▼ A computational model was developed to determine the dynamic behavior of counter flow compact heat exchangers. This code was written with the intention of becoming a component of a larger system dynamics model of a Brayton cycle nuclear power plant. Several configurations for the GT-MHR recuperator were analyzed, but the code can easily be modified to analyze many types of compact heat exchangers with a variety of applications. Helium was the working fluid used in this project, but the code can be modified to use other gases. This code was written in Matlab and Simulink but the methods outlined in this report could be easily reapplied in other programming languages. This code is also useful for designing counter flow compact heat exchangers in general. In this model the heat exchanger is discretized in time and in space. The resolution of the discretization is defined by the user. Helium properties are reevaluated for each volume before each time step. The dynamic inputs to the model are the inlet temperature, mass flow rate and pressure for each side of the heat exchanger. This model assumes low Mach number flows and treats the propagation of pressure and mass flow rate changes as instantaneous. The outlet temperature and pressure drop for each side is determined. The results of the simulation were successfully validated against results available in the literature. Contact the author for a copy of this code. Advisors/Committee Members: Blue, Thomas (Committee Chair).
Hawn, David Phillip. "Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink." 2009. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152.
Hawn, David Phillip. "Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink." 2009. Web. 22 Apr 2019.
Hawn DP. Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152.
2. Kulisek, Jonathan Andrew. The Effects of Nuclear Radiation on Schottky Power Diodes and Power MOSFETs.
▼ NASA is exploring the potential use of nuclear reactors as power sources for future space missions. These missions will require electrical components, consisting of power circuits and semiconductor devices, to be placed in close vicinity to the reactor, in the midst of a high neutron and gamma-ray radiation field. Therefore, the primary goal of this research is to examine the effects of a mixed neutron and gamma-ray radiation field on the static and dynamic electrical performance of power Schottky diodes and power MOSFETs in order to support future design efforts of radiation-hard power semiconductors and circuits. In order to accomplish this goal, commercial Si and 4H-SiC Schottky barrier power diodes were irradiated in the mixed neutron and gamma-ray radiation field of The Ohio State University research reactor (OSURR). The forward I-V characteristics were measured before and immediately after each successive radiation dose and the carrier-removal rates were compared, on the basis of NIEL, to a previous study, for which the same diode models were irradiated with a 203 MeV proton beam. In addition, a number of SiC Schottky barrier diodes were also irradiated in the OSURR and subsequently functionally tested in half-wave rectifier circuits, for which the voltage and current waveforms in the circuit were recorded. The results from the functional testing of these half-wave rectifier circuits were analyzed using results from I-V characterization, PSpice simulations, and an analytical formulation. In addition, boost and buck converters containing commercial power MOSFETs and Schottky diodes that were irradiated to various doses in a mixed neutron and gamma-ray radiation field, were tested. In addition to overall circuit performance in terms of output voltage and efficiency, the individual voltage and current waveforms of the MOSFET and diode in each circuit were examined. Radiation-induced changes in the switching characteristics of the MOSFETs were observed. Furthermore, changes in overall circuit performance and increased power dissipation in the MOSFETs during the over-voltage turn-off transient and on-state conduction portions of the switching cycle were observed. In addition to I-V characterization of the MOSFETs and diodes, PSpice simulations were performed in order to aid in the analysis and interpretation of the experimental results. Advisors/Committee Members: Blue, Thomas (Advisor).
Kulisek, Jonathan Andrew. "The Effects of Nuclear Radiation on Schottky Power Diodes and Power MOSFETs." 2010. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1267502877.
Kulisek, Jonathan Andrew. "The Effects of Nuclear Radiation on Schottky Power Diodes and Power MOSFETs." 2010. Web. 22 Apr 2019.
Kulisek JA. The Effects of Nuclear Radiation on Schottky Power Diodes and Power MOSFETs. [Internet] [Doctoral dissertation]. The Ohio State University; 2010. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1267502877.
3. Khorsandi, Behrooz. Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation.
▼ There is considerable interest in developing a power monitor system for Generation IV reactors (for instance GT-MHR). A new type of semiconductor radiation detector is under development based on silicon carbide (SiC) technology for these reactors. SiC has been selected as the semiconductor material due to its superior thermal-electrical-neutronic properties. Compared to Si, SiC is a radiation hard material; however, like Si, the properties of SiC are changed by irradiation by a large fluence of energetic neutrons, as a consequence of displacement damage, and that irradiation decreases the life-time of detectors. Predictions of displacement damage and the concomitant radiation effects are important for deciding where the SiC detectors should be placed. The purpose of this dissertation is to develop computer simulation methods to estimate the number of various defects created in SiC detectors, because of neutron irradiation, and predict at what positions of a reactor, SiC detectors could monitor the neutron flux with high reliability. The simulation modeling includes several well-known – and commercial – codes (MCNP5, TRIM, MARLOWE and VASP), and two kinetic Monte Carlo codes written by the author (MCASIC and DCRSIC). My dissertation will highlight the displacement damage that may happen in SiC detectors located in available positions in the OSURR, GT-MHR and IRIS. As extra modeling output data, the count rates of SiC for the specified locations are calculated. A conclusion of this thesis is SiC detectors that are placed in the thermal neutron region of a graphite moderator-reflector reactor have a chance to survive at least one reactor refueling cycle, while their count rates are acceptably high. Advisors/Committee Members: BLUE, Thomas (Advisor).
Khorsandi, Behrooz. "Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation." 2007. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438.
Khorsandi, Behrooz. "Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation." 2007. Web. 22 Apr 2019.
Khorsandi B. Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation. [Internet] [Doctoral dissertation]. The Ohio State University; 2007. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438.
4. Baas, Larry Brandon. Feasibility Study of Concept Designs for Photonic Radiation Detection.
▼ The objective of this research is to do a feasibility study on a photonic-based semiconductor concept design for a radiation detector. The research was funded by the National Science Foundation in conjunction with the Department of Homeland Security. It was a cooperative effort between the Nuclear Engineering Program and the Electrical and Computer Engineering Department at Ohio State University. There are two concept device configurations considered in this study, the critical angle setup and the Fabry-Perot setup. In addition to being able to detect radiation, the device should be portable, durable and user friendly for field use. Its initial purpose is to be used to detect gamma radiation, but it is not limited to this purpose. Semiconductors have already been successfully used in highly sensitive radiation detectors (e.g. germanium detectors). The perceived advantage is that photonics can possibly be used to make a sensitive detector that can operate while at room temperature and be only slightly affected by electromagnetic interference due to its operating nature. Two semiconductor materials, silicon and cadmium telluride, were analyzed in detail, while others were considered as possibilities for later research. Following the development of an analytical model, experimental data were taken to validate the model. The experiments were performed for silicon because it is the least expensive of the candidate semiconductor materials. Advisors/Committee Members: Blue, Thomas (Advisor).
Baas, Larry Brandon. "Feasibility Study of Concept Designs for Photonic Radiation Detection." 2009. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1245376171.
Baas, Larry Brandon. "Feasibility Study of Concept Designs for Photonic Radiation Detection." 2009. Web. 22 Apr 2019.
Baas LB. Feasibility Study of Concept Designs for Photonic Radiation Detection. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1245376171.
5. Bettencourt, Michael E. Fluidic and Neutronic Coupled Modeling of the Space Molten Salt Reactor Concept.
▼ The power needs for advanced future space missions necessitate the development of high energy density, long term power sources. Research at The Ohio State University under the NASA Ralph Steckler Space Grant Colonization Research and Technology Development Opportunity has identified molten salt reactors (MSRs) as a potentially appealing technology for high power, high temperature space fission systems. Modeling of MSR technology presents unique challenges not present in solid fueled reactor technology such as light water reactors. This thesis presents the development of coupled neutronic and fluid dynamic, multiphysics, modeling of liquid fueled nuclear reactor technology and the modeling of a molten salt reactor.The results of the multiphysics modeling show significant differences in the neutronic and temperature distributions of the reactor core between the independent models and the coupled results. Advisors/Committee Members: Blue, Thomas (Advisor).
Bettencourt, Michael E. "Fluidic and Neutronic Coupled Modeling of the Space Molten Salt Reactor Concept." 2013. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1385483774.
Bettencourt, Michael E. "Fluidic and Neutronic Coupled Modeling of the Space Molten Salt Reactor Concept." 2013. Web. 22 Apr 2019.
Bettencourt ME. Fluidic and Neutronic Coupled Modeling of the Space Molten Salt Reactor Concept. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1385483774.
6. Petrie, Christian M. Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra.
▼ ISO standard 4037 specifies that for calibrating protection level dosimeters, scattered radiation should contribute less than 5 percent of the exposure. In previous work, we reported the results of an MCNP analysis of the shadow shield technique that was performed for a calibration range with a Cs-137 irradiator. This thesis examines the energy distribution of the photons contributing to the exposure percent scatter (S%) and the detailed origin of the scatter that originates in the irradiator. In summary, it reports that: 1) the majority of S% is due to photons with energies that are significantly below the source energy, 2) a significant percentage of S% is due to photons that scatter within the source and source capsule walls, and 3) S% due to scatter within the irradiator is even more significant than we previously reported. Advisors/Committee Members: Blue, Thomas (Advisor).
Petrie, Christian M. "Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra." 2011. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1313095840.
Petrie, Christian M. "Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra." 2011. Web. 22 Apr 2019.
Petrie CM. Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra. [Internet] [Masters thesis]. The Ohio State University; 2011. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1313095840.
7. Garcia, Timothy Richard. Fabrication, characterization and simulation of 4H-SiC Schottky diode alpha particle detectors for pyroprocessing actinide monitoring.
▼ Pyroprocessing is a method of using high-temperature molten salts and electric fields to separate and collect fuel isotopes of used nuclear fuel. It has been has been tested in the U.S. at Idaho National Laboratory as a key step in closing the nuclear fuel cycle. One technical problem with the pyroprocessing method is a lack of knowledge regarding the actinide concentrations in the salt bath during operation, since on-line techniques for measuring these concentrations are not presently available. 4H-SiC Schottky diode detectors can potentially fulfill this need. Such detectors would operate in contact with the molten salt, and measure concentrations via alpha-particle spectroscopy. This work seeks to fabricate and characterize 4H-SiC Schottky diode detectors at high temperature, model the alpha particle spectrum expected in a molten salt, and model the operation of the detectors to confirm the physics of operation is as expected.In this work, 4H-SiC Schottky diode detectors were fabricated at OSU Nanotech West. After fabrication, these detectors were characterized using both I-V curves and Am-241 alpha-particle energy spectra. All measurements were made as a function of temperature, from room temperature up to 500°C. The average energy required to create an electron-hole pair was observed to decrease with an increase of temperature, due to a decrease of both the 4H-SiC bandgap and non-linear energy loss terms. Furthermore, the FWHM of the spectra was observed to be dependent on the leakage current at a certain temperature, and not dependent on the temperature itself.Secondly, the alpha particle energy spectrum in the pyroprocessing environment was modeled using SRIM. The molten salt was modeled in 3 different geometries, with or without a protective cover material on top of the detector. Due to the loss of alpha-particle energy in the molten salt itself, a high-energy alpha emitter may completely cover the spectrum from a lower-energy alpha emitter. Each of the geometries simulated showed a different sensitivity to the lower-energy alpha emitter. Regardless of which geometry was modeled, it was observed that it is possible to measure both the emission energy of the alpha particles, as well as the concentration of the alpha emitter in the liquid.Lastly, Sentaurus TCAD was used to simulate the detection of alpha-particle charge collection in situations that are relevant to the molten salt alpha particle energy spectra. The effect of electric field negation was investigated, as well as velocity saturation. Finally, the dependence of charge recombination on temperature, alpha particle energy, and angle of incidence was investigated. These simulations captured the measurements performed at room temperature. With changed angle of incidence, the change in the amount of charge collected was less than 1 percent, indicating a weak dependence. Also, the amount of charge lost to Auger recombination was seen to increase with temperature. This disagrees with observations from experiment, indicating that the temperature dependence… Advisors/Committee Members: Blue, Thomas (Advisor).
Garcia, Timothy Richard. "Fabrication, characterization and simulation of 4H-SiC Schottky diode alpha particle detectors for pyroprocessing actinide monitoring." 2014. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1387490688.
Garcia, Timothy Richard. "Fabrication, characterization and simulation of 4H-SiC Schottky diode alpha particle detectors for pyroprocessing actinide monitoring." 2014. Web. 22 Apr 2019.
Garcia TR. Fabrication, characterization and simulation of 4H-SiC Schottky diode alpha particle detectors for pyroprocessing actinide monitoring. [Internet] [Doctoral dissertation]. The Ohio State University; 2014. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1387490688.
8. Stone, Stephen E. A Study of the Effects of Neutron Irradiation and Low Temperature Annealing on the Electrical Properties of 4H Silicon Carbide.
▼ Recent advancements in growth technology have made silicon carbide (SiC) a feasible option for use as a semiconductor material in electronic devices. Its mechanical and electrical properties make it a desirable choice for high-power high-frequency devices as well as for use in harsh environments. It is therefore necessary to understand the response of SiC's electrical properties to radiation induced damage. The effects of neutron irradiation on the electrical properties of highly doped 4H SiC were studied. Bulk 4H SiC with a low resistivity of ~0.018O-cm was utilized in this work. The material was fabricated into standard Hall bars for characterization of the material's resistivity, free carrier concentration and electron Hall mobility as a function of 1 MeV neutron equivalent fluence. Also investigated were the post irradiation effects of low temperature annealing (175C) on the same properties. It was found that the material's resistivity doubled as fluences of 2.7x1016cm-2 were reached and did not incur any significant recovery as a function of annealing. It was also found that this material suffers from a carrier removal rate of ~48.5 n cm-1 when related linearly to 1 MeV fluence. This reduction in free carrier concentration was attributed to defects locally deactivating donor sites in the material. These defects were unstable at low temperatures as the carrier concentration recovered completely as a result of the annealing process. The Hall mobility was also found to degrade with fluence. At room temperature this degradation is a combination of an increase in mobility due to neutralized donors and a decrease due to increased scattering from electrically inactive defects. These electrically inactive defects were found to be stable at 175C and were the major contributor to the stable long term increase in resistivity. Advisors/Committee Members: Blue, Thomas (Advisor).
Stone, Stephen E. "A Study of the Effects of Neutron Irradiation and Low Temperature Annealing on the Electrical Properties of 4H Silicon Carbide." 2008. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1211898142.
Stone, Stephen E. "A Study of the Effects of Neutron Irradiation and Low Temperature Annealing on the Electrical Properties of 4H Silicon Carbide." 2008. Web. 22 Apr 2019.
Stone SE. A Study of the Effects of Neutron Irradiation and Low Temperature Annealing on the Electrical Properties of 4H Silicon Carbide. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1211898142.
9. Reinke, Benjamin T. Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool.
▼ A Cryogenic Irradiation Facility (CRIF) has been designed, fabricated, and tested for use in the pool of the Ohio State University Research Reactor (OSURR). This CRIF will support in situ radiation induced damage experiments in optical and electronic materials from cryogenic temperatures and temperature controlled low temperature annealing experiments from cryogenic temperatures to above room temperature. The facility has been tested with liquid nitrogen and liquid helium out of the reactor pool. Temperature control has been demonstrated in the experimental volume of the CRIF from 4.2 K to above room temperature. The 10" Dry Tube, which will house the CRIF in the OSURR pool, has been inserted into OSURR pool and tested. The empty 10" Dry Tube and the CRIF have been simulated in a model of the OSURR using MCNP6 to understand the predicted radiation fields and total energy deposition in the empty 10" Dry Tube and in typical optical and electronic materials in the experimental volume of the CRIF. The radiation fields and the total radiation energy deposition have been used to predict experimental operating parameters for future CRIF experiments, based upon desired dose calculations and time to boil-off for the liquid helium inside the CRIF. Advisors/Committee Members: Blue, Thomas (Advisor).
Reinke, Benjamin T. "Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool." 2015. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576.
Reinke, Benjamin T. "Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool." 2015. Web. 22 Apr 2019.
Reinke BT. Design, Characterization, and Simulation of a Cryogenic Irradiation Facility in the Ohio State University Research Reactor Pool. [Internet] [Masters thesis]. The Ohio State University; 2015. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1437746576.
10. Chaleff, Ethan S. The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors.
▼ Molten salts, such as the fluoride salt eutectic LiF-NaF-KF (FLiNaK) or the transition metal fluoride salt KF-ZrF4, have been proposed as coolants for numerous advanced reactor concepts. These reactors are designed to operate at high temperatures where radiative heat transfer may play a significant role. If this is the case, the radiative heat transfer properties of the salt coolants are required to be known for heat transfer calculations to be performed accurately. Chapter 1 describes the existing literature and experimental efforts pertaining to radiative heat transfer in molten salts. The physics governing photon absorption by halide salts is discussed first, followed by a more specific description of experimental results pertaining to salts of interest. The phonon absorption edge in LiF-based salts such as FLiNaK is estimated and the technique described for potential use in other salts. A description is given of various spectral measurement techniques which might plausibly be employed in the present effort, as well as an argument for the use of integral techniques. Chapter 2 discusses the mathematical treatments required to approximate and solve for the radiative flux in participating materials. The differential approximation and the exact solutions to the radiative flux are examined, and methods are given to solve radiative and energy equations simultaneously. A coupled solution is used to examine radiative heat transfer to molten salt coolants. A map is generated of pipe diameters, wall temperatures, and average absorption coefficients where radiative heat transfer will increase expected heat transfer by more than 10% compared to convective methods alone. Chapter 3 presents the design and analysis of the Integral Radiative Absorption Chamber (IRAC). The IRAC employs an integral technique for the measurement of the entire electromagnetic spectrum, negating some of the challenges associated with the methods discussed in Chapter 1 at the loss of spectral information. The IRAC design is validated by modeling the experiment in Fluent which shows that the IRAC should be capable of measuring absorption coefficients within 10%. Chapter 4 contains a parallel effort to experimental techniques, whereby information on absorption in salts is pursued using the Density Functional Theory code VASP. Photon-electron interactions are studied in pure salts such as LiF and are shown to be broadly transparent. Transition metal Fluoride salts such as KF-ZrF4 are shown to be broadly opaque. The addition of small amounts of transition metal impurities is studied by insertion of Chromium into the salt mixtures, which causes otherwise transparent salts to exhibit absorption coefficients significant to heat transfer. The spectral absorption coefficient for FLiNaK with Chromium is presented as is the average absorption coefficient as a function of impurity concentration. Chapter 5 discusses experimental efforts undertaken at The Ohio State University. Challenges with the constructed experimental apparatus are discussed and suggestions for… Advisors/Committee Members: Blue, Thomas (Advisor).
Chaleff, Ethan S. "The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors." 2016. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113.
Chaleff, Ethan S. "The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors." 2016. Web. 22 Apr 2019.
Chaleff ES. The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors. [Internet] [Doctoral dissertation]. The Ohio State University; 2016. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113.
11. Taylor, Neil Rutger. Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors.
▼ Fission chambers are a vital instrument for the power monitoring of nuclear reactors, and as the current generation of reactors age, the need for next generation reactors to come online grows. Along with these new reactors, sensors and instruments are required for safe operation. One such instrument is a fission chamber capable of surviving the elevated temperatures and harsh environments that come with the next fleet of reactors. A high temperature fission chamber (HTFC) was designed in collaboration with Oak Ridge National Lab to fill this demand for new technology. This design was modeled using MCNP6 and an experiment was conducted at the Ohio State University Research Reactor to test the measurement capabilities of the design. MCNP6 was utilized to simulate expected fission rates from the HTFC at a variety of power levels and locations around the OSURR. These results were then used to create a reactor test plan utilizing the different locations and power levels to test the operation of the HTFC in both pulse and current mode operation. Along with these simulations, a detailed activation analysis utilizing the ORIGEN module within SCALE 6.1 was performed to determine the expected activity level and dose rates associated with the reactor experiment. A gas sampling system was developed to sample gas flowed through the experimental apparatus to ensure that the HTFC survived the experiment. This sampling system monitored the flow gas for alpha and beta radiation from fission products that would have leaked out of the containment in case of failure. Advisors/Committee Members: Blue, Thomas (Advisor).
Taylor, Neil Rutger. "Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors." 2017. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1512048679402356.
Taylor, Neil Rutger. "Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors." 2017. Web. 22 Apr 2019.
Taylor NR. Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors. [Internet] [Masters thesis]. The Ohio State University; 2017. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1512048679402356.
12. Birri, Anthony. Investigation of the Combined Effects of Simultaneous Heating and Bending of Silica Optical Fiber.
▼ Optical fibers have the unique application of distributed sensing in harsh environments. Optical fibers may be used for spatially distributed sensing of temperature, strain, pressure, as well as other related physical quantities. For this reason, optical fibers have potential for facility monitoring, materials testing, the collection of Big Data, and experimental research. Optical fibers can withstand extremely high temperatures (temperature limits around 1000 °C for silica fiber, and around 1400 °C for sapphire fiber), which make them of particular interest for industries such as the nuclear industry and the petroleum industry. In fact, the U.S. Department of Energy has expressed interest in the utilization of optical fibers of next-generation instrumentation of nuclear reactors. Due to promising aspects of optical fibers for harsh environment sensing, it is necessary to understand the behavior of optical fiber in such harsh environments. Optical fibers will undergo extremely high temperatures if utilized in many of the next-generation reactor designs. Also, it is likely that a fiber will undergo some degree of bending in their implementation. The focus of this work is the simultaneous effects of heating and bending silica optical fiber. This work should act as an expansion on the current knowledge that exists in literature for unbent (or at least insignificantly bent) fiber heated at extremely high temperatures.In this work, multimode and single-mode silica fibers have been tested in a high temperature setting, while simultaneously experiencing a bend. The range of temperature tested was 500-1000° C and the bend radii considered were 1.27, 2.54, and 3.81 cm (0.5, 1.0, and 1.5 inches). Multimode fiber (MMF) was analyzed for transmission, while single-mode fiber (SMF) was both analyzed for transmission and interpreted by optical backscatter reflectometry. Attenuation was observed to increase in MMF with increasingly high temperatures and tighter bend radii. SMF was far more resilient to transmission loss than MMF, under similar conditions of temperature and curvature. Optical backscatter reflectometry was performed for bent SMF up to 1100 °C, and revealed evidence that, at high temperatures, bends in fiber can enhance devitrification that can inhibit light transmission through the fiber. This work suggests that the devitrification process begins at the surface of the fiber and moves inward. Moreover, this work suggests that bend stress applied to surface flaws of the fiber leads to significantly higher crystallization rates at temperatures at which silica does not typically devitrify so rapidly. Advisors/Committee Members: Blue, Thomas (Advisor).
Birri, Anthony. "Investigation of the Combined Effects of Simultaneous Heating and Bending of Silica Optical Fiber." 2018. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1523878305649017.
Birri, Anthony. "Investigation of the Combined Effects of Simultaneous Heating and Bending of Silica Optical Fiber." 2018. Web. 22 Apr 2019.
Birri A. Investigation of the Combined Effects of Simultaneous Heating and Bending of Silica Optical Fiber. [Internet] [Masters thesis]. The Ohio State University; 2018. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1523878305649017.
13. Abejon Orzaez, Jorge. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.
▼ The objective of this research is to, based on the original design for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), develop an MCNPX model of the reactor core with the objective to attain criticality and to breed new fuel. A brief but complete description of a first approach to the PB-AHTR will be provided and a MCNPX model will be run in order to ascertain the difficulties of that configuration. On the second part, a modification of the original model will be evaluated and compared in order to resolve the difficulties encountered in the original design. Finally, in an effort to optimize the design, an evolutionary approach will be analyzed, based on the previous model, and conclusions will be attained Advisors/Committee Members: Blue, Thomas (Committee Chair), Sun, Xiaodong (Committee Co-Chair).
Abejon Orzaez, Jorge. "Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor." 2009. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.
Abejon Orzaez, Jorge. "Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor." 2009. Web. 22 Apr 2019.
Abejon Orzaez J. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.
14. Chenkovich, Robert Jeremy. Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes.
▼ The objective of this work is to provide more accurate neutronic models of the OSU research reactor and also to provide a more complete characterization of the energy-dependent neutron flux spectrum present at the various experimental facilities of the reactor. This work will allow for a better predictive capability, so that experimental results can be better anticipated. Two models are analyzed, one with a very detailed core geometry, the other with a more homogenized core. The two models were refined and made to be more accurate in various ways. Also, experimental benchmarking of these computer models is included, specifically using material activation experiments and spectral deconvolution (or unfolding) codes. In these programs, the wires' post-irradiation activities, their response functions, and an initial guess of the energy-dependent neutron flux spectrum are input into an iterative process, which outputs a energy-dependent neutron flux spectrum. The experimental and predicted energy-dependent neutron flux spectra are then compared to illustrate the differences between models. Advisors/Committee Members: Aldemir, Tunc (Committee Co-Chair), Blue, Thomas (Advisor).
Chenkovich, Robert Jeremy. "Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes." 2008. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975.
Chenkovich, Robert Jeremy. "Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes." 2008. Web. 22 Apr 2019.
Chenkovich RJ. Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975.
15. Wilson, Brandon Augustus. Evaluation of Optical Fiber Sensors in High Temperature and Nuclear Reactor Environments.
▼ The Department of Energy and Idaho National Laboratory are restarting the TREAT reactor and are interested in updating the reactor's instrumentation regarding the analysis of the test fuel. Optical fibers' ability to make distributed temperature measurements coupled with its small footprint makes optical fiber a viable candidate to monitor fuel performance in the TREAT reactor. In addition to TREAT reactor, the U.S. Department of Energy and nuclear reactor companies like TerraPower have shown interest in using distributed optically based instrumentation for nuclear instrumentation in Next-gen reactors. The performance and evaluation of optical fiber based instrumentation in high temperature and radiation environments is the main goal of this work. A feasibility study to determine the viability of extending this technology to the nuclear field was made. In addition to the performance testing of commercial optical fiber based instrumentation, I was able to modify and innovate various aspects of the optical fiber based instrumentation, so that it could survive the high temperature and radiation environments of a Next-Gen reactor.Distributed temperature sensing using optical fiber based methods in silica optical fibers was found to have a temperature limit of around 700 C. Above the 700 C mark, various effects, from annealing of the glass to environmental effects from the atmosphere, start to cause sensing failure in the fiber. This temperature limit can be extended to 1000 C if the silica optical fiber is placed in an inert environment with a micro capillary tube or high temperature coating to support it mechanically. Distributed temperature sensing with commercial optical fibers was also tested in a reactor environment and was found to incur a sensing failure after a neutron fluence of around 1018 n/cm2. Radiation hardness can be added to the distributed sensing ability of optical fibers by placing Bragg gratings into the fiber. The high reflective signature off of the Bragg gratings in the fiber allows the distributed temperature sensing to continue to provide accurate measurements, even when the noise floor from radiation damage is increased in the fiber. Femtosecond Bragg gratings have the most potential for long term use in a nuclear reactor, since they were shown to survive long periods of high temperature and radiation fluences without much degradation.Sapphire fiber was also analyzed in this work for its suitability as optical instrumentation in Next-Gen reactors. Sapphire fiber has a temperature limit of 1300 C for light transmission in the fiber. Above 1300 C, aluminum oxyhydroxide forms on the surface of the fiber, causing massive light attenuation in the fiber. An inert atmosphere can extend the temperature range of sapphire optical fibers and sapphire instrumentation above 1300 C. Distributed temperature sensing with sapphire fiber was also achieved in this work by creating an internal reflective cladding using, high energy ion implantation in the fiber. This internal reflective cladding creates a graded… Advisors/Committee Members: Blue, Thomas (Advisor).
Wilson, Brandon Augustus. "Evaluation of Optical Fiber Sensors in High Temperature and Nuclear Reactor Environments." 2017. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1483626659096251.
Wilson, Brandon Augustus. "Evaluation of Optical Fiber Sensors in High Temperature and Nuclear Reactor Environments." 2017. Web. 22 Apr 2019.
Wilson BA. Evaluation of Optical Fiber Sensors in High Temperature and Nuclear Reactor Environments. [Internet] [Doctoral dissertation]. The Ohio State University; 2017. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1483626659096251.
16. Zelaski, Alexandra R. Development of a Silicon Carbide Schottky Diode Detector for Use in Determining Actinide Inventories based on Alpha Particle Spectroscopy.
▼ Deployment of Generation IV nuclear power will require novel materials as well as new techniques for monitoring plant functions. Reprocessing of spent nuclear fuel will play a large role in the future generations of reactors. It would be useful if real-time measurements of actinide concentrations during reprocessing could be achieved through alpha spectroscopy. Devices built upon silicon carbide offer the best hope of surviving the harsh chemical, and high radiation and high temperature environments associated with reprocessing. In this project 4H-SiC alpha particle detectors were built and tested up to high temperature in order to simulate some of the conditions a detector might encounter in the pyroprocessing environment. The silicon carbide used in this project had a low-doped (5x1014 atoms/cm3 of nitrogen) 21 micron thick epitaxial layer grown on top of a 300 micron thick bulk substrate with a nitrogen doping concentration of 1x1018 atoms/cm3. 100 nm of nickel, 10 nm of titanium, and 10 nm of gold were deposited, in that order, on the epitaxial side and annealed to form a Schottky contact. An ohmic contact was formed by annealing from 100 nm of nickel deposited on the substrate and annealed. The devices were characterized through IV curve measurements and then exposed to Am-241 alpha particles and high temperature while in vacuum. Mixed results show that these detectors can operate up to 100 degrees Celsius with very little change in peak location, full width half max (FWHM) and energy resolution. The FWHM remained below 100 keV, while the energy resolution was below 1.57%. At 150 degrees Celsius, the FWHM remained below 190 keV while the energy resolution was below 3.46%. Temperatures above 150 degrees Celsius pose significant problems to the current design as the alpha peak moves to lower channels and broadens to have a full width half max between 300 and 500 keV. The current state of literature on SiC Schottky diode detectors shows that no other Schottky diode detectors have been tested up to higher temperatures with a better resolution. Advisors/Committee Members: Blue, Thomas E. (Advisor).
Zelaski, Alexandra R. "Development of a Silicon Carbide Schottky Diode Detector for Use in Determining Actinide Inventories based on Alpha Particle Spectroscopy." 2011. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1316486528.
Zelaski, Alexandra R. "Development of a Silicon Carbide Schottky Diode Detector for Use in Determining Actinide Inventories based on Alpha Particle Spectroscopy." 2011. Web. 22 Apr 2019.
Zelaski AR. Development of a Silicon Carbide Schottky Diode Detector for Use in Determining Actinide Inventories based on Alpha Particle Spectroscopy. [Internet] [Masters thesis]. The Ohio State University; 2011. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1316486528.
17. Brown, Curtis A. Gamma Spectroscopic Method to Assess Radium Concentrations in Drill Cuttings and Water Produced by Hydraulic Fracturing.
▼ Primordial terrestrial radiation is mainly a consequence of the radioactive decay of nuclei in three naturally occurring decay series known as uranium series, actinium series, and thorium series. The parent nuclei along with the progeny (decay products) of these decay series can be found in various concentrations in Earth's crust. Among the progeny, 226Ra is of greatest concern. 226Ra is water soluble and it decays to 222Rn which is a gas, which allows these two radionuclides to migrate considerable distances. 226Ra is found in shale at relatively high concentrations compared to other rock formations making shale a naturally occurring radioactive material (NORM). One concern with hydraulic fracturing is that the extraction of the gas embedded in the shale formation buried deep within Earth's crust is bringing radioactive nuclides to Earth's surface. This thesis is focused on the development of gamma-ray spectroscopic methods to determine the radium concentration in drill cuttings and water that is produced by hydraulic fracturing. The methods rely upon the development of secular equilibrium between 226Ra and its progeny. Only the countrate of the 214Bi 609 keV gamma-rays is counted and compared to the countrate of 137Cs activity doped in standards. Measurement methods are unique in that two factors are used to correct for the varying sample attenuation of the 214Bi 609 keV gamma-ray resulting from varying compositions and densities in each sample. Measurements are made with a 137Cs point source that is placed on top of the sample and is used for one correction factor, and Monte Carlo simulations of the response of an HPGe gamma-ray detector are used for the other correction factor. For a representative drill cutting sample, the product of the correction factors equals approximately 0.89. For a representative water sample, the product of the correction factors equals approximately 1.17. Advisors/Committee Members: Blue, Thomas (Advisor).
Brown, Curtis A. "Gamma Spectroscopic Method to Assess Radium Concentrations in Drill Cuttings and Water Produced by Hydraulic Fracturing." 2016. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1457700818.
Brown, Curtis A. "Gamma Spectroscopic Method to Assess Radium Concentrations in Drill Cuttings and Water Produced by Hydraulic Fracturing." 2016. Web. 22 Apr 2019.
Brown CA. Gamma Spectroscopic Method to Assess Radium Concentrations in Drill Cuttings and Water Produced by Hydraulic Fracturing. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1457700818.
18. Hawn, David Phillip. The Effects of High Temperature and Nuclear Radiation on the Optical Transmission of Silica Optical Fibers.
▼ Distributed measurements made with fiber optic instrumentation have the potential to revolutionize data collection for facility monitoring and process control in industrial environments. Dozens of sensors etched into a single optical fiber can be used to instrument equipment and structures so that dozens of spatially distributed temperature measurements, for example, can be made quickly using one optical fiber. Optically based sensors are commercially available to measure temperature, strain, and other physical quantities that can be related to strain, such as pressure and acceleration. Other commercially available technology eliminates the need to etch discrete sensors into an optical fiber and allows temperature measurements to be made along the length of an ordinary silica fiber. Distributed sensing with optical instrumentation is commonly used in the petroleum industry to measure the temperature and pressure profiles in down hole applications. The U.S. Department of Energy is interested in extending the distributed sensing capabilities of optical instrumentation to high temperature reactor radiation environments. For this technology extension to be possible, the survivability of silica optical fibers needed to be determined in this environment. In this work the optical attenuation added to silica optical fiber exposed simultaneously to reactor radiation and temperatures to 1000°C was experimentally determined. Optical transmission measurements were made in-situ from 400nm-2300nm. For easy visualization, all of the results generated in this work were processed into movies that are available publicly . In this investigation, silica optical fibers were shown to survive optically and mechanically in a reactor radiation environment to 1000°C. For the combined high temperature reactor irradiation experiments completed in this investigation, the maximum attenuation increase in the low-OH optical fibers was around 0.5db/m at 1550nm and 0.6dB/m at 1300nm. The radiation induced optical attenuation primarily affected wavelengths less than 1000nm and this attenuation cannot be avoided in silica. Thermal effects dominated the increase in attenuation at wavelengths above 1000nm and it may be possible to mitigate these effects. Fortuitously, commercial optical instrumentation typically utilizes wavelengths centered around 1300nm and 1550nm where the radiation induced attenuation was minimal. The maximum continuous use temperature of silica optical fiber may be limited to 900°C with intermittent use to 1000°C. The silica optical fibers tested in this project are inexpensive and commercially available. Optical sensors were not tested in this project and development and testing of radiation hard optical sensors is recommended as future work. Advisors/Committee Members: Blue, Thomas (Advisor).
Hawn, David Phillip. "The Effects of High Temperature and Nuclear Radiation on the Optical Transmission of Silica Optical Fibers." 2012. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1345066048.
Hawn, David Phillip. "The Effects of High Temperature and Nuclear Radiation on the Optical Transmission of Silica Optical Fibers." 2012. Web. 22 Apr 2019.
Hawn DP. The Effects of High Temperature and Nuclear Radiation on the Optical Transmission of Silica Optical Fibers. [Internet] [Doctoral dissertation]. The Ohio State University; 2012. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1345066048.
19. Wood, Thomas W, Jr. Evaluation of Single-Mode and Bragg Grating Optical Fibers Interrogated with an Optical Backscatter Reflectometer (OBR) in High Temperature Environments for Advanced Instrumentation in Nuclear Reactors.
▼ Optical fibers have made a drastic change in the telecommunications industry and in the more recent past have been developed and applied in making engineering measurements. Optical fibers have been used for various engineering measurement applications under harsh environments and this work explores the use of optical fiber sensors in the nuclear industry. In this work, inexpensive single-mode silica optical fibers, as well as Bragg Grating optical fibers, were interrogated with Luna Innovations' Optical Backscatter Reflectometer (OBR) to perform distributed temperature measurements at temperatures up to 1000°C. Measurements of the backscattered signal were taken continuously to determine the amount of light that is backscattered as a function of temperature and position along the length of the fiber. This data was post-processed to determine the spectral shift in the Rayleigh backscatter signature. The spectral shift data was then calibrated to a change in temperature. This work found that the temperature sensing mechanism that utilizes the Fiber Bragg Gratings provides a reliable measurement at temperatures up to 100°C but at higher temperatures the measurement begins to fail. This work also determines an upper operational temperature limit of 500°C for the distributed measurement technique based on Rayleigh backscatter using Corning's SMF-28e+ commercially available single-mode fiber. Advisors/Committee Members: Blue, Thomas (Advisor).
Wood, Thomas W, Jr. "Evaluation of Single-Mode and Bragg Grating Optical Fibers Interrogated with an Optical Backscatter Reflectometer (OBR) in High Temperature Environments for Advanced Instrumentation in Nuclear Reactors." 2013. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1373364266.
Wood, Thomas W, Jr. "Evaluation of Single-Mode and Bragg Grating Optical Fibers Interrogated with an Optical Backscatter Reflectometer (OBR) in High Temperature Environments for Advanced Instrumentation in Nuclear Reactors." 2013. Web. 22 Apr 2019.
Wood, Thomas W J. Evaluation of Single-Mode and Bragg Grating Optical Fibers Interrogated with an Optical Backscatter Reflectometer (OBR) in High Temperature Environments for Advanced Instrumentation in Nuclear Reactors. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1373364266.
20. Breuning, David. A Low-Level Radioactive Waste Management Program for Activated Waste from he GE PETrace™ Cyclotron.
▼ Preventative Maintenance and Operational Use of the 16.5 MeV GE PETrace™ Cyclotron, used for the production of 18F and other radioisotope labeled pharmaceuticals, produces long-lived activated waste products which must be classified by radionuclide and activity before disposal as Low-Level Radioactive Waste (LLRW). Large volumes of this waste can be created in a busy cyclotron facility, but full gamma spectrometric analysis of all of the waste is expensive, and excessive handling of the waste is counter to the As Low As Reasonably Achievable (ALARA) concept. However, analysis of representative waste components allows them to be classified into categories in a manner such that all components in any category contain similar radioisotopic content. Radioisotopic activity and exposure rate measurements of representative samples of each of these categories can be used as standards to create conversion factors for each radionuclide in each category in units of activity per unit exposure rate. Subsequent future waste assumes that similar processes produce similar mixtures of radioisotopes, allowing this future waste to placed in the same category in which the standard was placed. This thesis assesses with what accuracy an estimate of the maximum possible isotopic activity of the waste can be determined by taking exposure rate measurements of future waste and multiplying the measured exposure rates by each conversion factor for each radionuclide for the category. The results of the assessment are that for Niobium and Silver Targets, Vacuum Tank and Ion Source Rags, Delivery Lines and other Delivery System Components, Chimneys and Pullers, Vacuum Tank Rods and Seals, Collimators and Baffles, and Extraction Foils and Fittings an estimate of the maximum possible isotopic activity of the waste, can be determined with sufficient accuracy to allow it to be disposed of as LLRW Advisors/Committee Members: Blue, Thomas (Advisor).
Breuning, David. "A Low-Level Radioactive Waste Management Program for Activated Waste from he GE PETrace™ Cyclotron." 2010. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1260557462.
Breuning, David. "A Low-Level Radioactive Waste Management Program for Activated Waste from he GE PETrace™ Cyclotron." 2010. Web. 22 Apr 2019.
Breuning D. A Low-Level Radioactive Waste Management Program for Activated Waste from he GE PETrace™ Cyclotron. [Internet] [Masters thesis]. The Ohio State University; 2010. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1260557462.
21. Jarrell, Joshua Taylor. High Temperature Characterization and Endurance Testing of Silicon Carbide Schottky Barrier Alpha Detectors.
▼ AbstractThere is a need for alpha detection systems which can operate in high temperature environments for long periods of time. The needs include the measurement of actinide concentrations in reprocessing of nuclear waste by means of pyroprocessing as well as in molten salt reactors. Silicon carbide is well suited to high temperature applications, has good corrosion resistance, has a wide band gap, and being a semiconductor material, when used on a particle detector exhibits high stopping power for charged particles in comparison to gas-filled detectors. As a result of these material properties, silicon carbide Schottky diodes are well suited to alpha particle detection and identification in high temperature environments.In this research, 4H-SiC alpha detectors with two different Schottky contact compositions were prepared and tested under various conditions. Each detector had either a nickel-titanium-gold Schottky contact or a platinum Schottky contact. The Schottky diode detectors had an ohmic nickel contact. Using an Am-241 alpha source in a vacuum chamber, the FWHM, diffusion length, and charge collection efficiency at varying voltages of each detector was determined and the behavior of these characteristics at temperatures from 20°C to 500°C was observed. The detectors were characterized using current-voltage, capacitance-voltage, and alpha spectroscopy measurements. The diffusion length was calculated as a free parameter during the charge collection efficiency calculation. Full charge collection was demonstrated at a bias voltage of -200 volts for nickel-titanium-gold detectors. The average FWHM for nickel-titanium-gold detectors was 3.5% (192 keV) for 5485 keV alpha particles at 500º Celsius with a peak resolution of 0.91% (50 keV). The FWHM for platinum Schottky contact detectors was found to be approximately 2% (110 keV) at the same incident alpha energy. Both types of detectors were subjected to long-term endurance testing at 500°C for a maximum of 168 hours. The change in performance of each detector was observed through analysis of the behavior of the FWHM, leading up to total failure of the device or end of the test period. Subsequent changes post cooling were observed as indicated by the current-voltage characterization taken at room temperature. Finally, a variation of the nickel-titanium-gold Schottky contact detectors was fabricated at a smaller diameter in order to reduce leakage current from the detector's surface. This variant displayed a greater resistance to long term high temperature operation than the larger nickel-titanium-gold detectors with which it was produced, but not greater than the resistance of the highest performing large detectors that were fabricated separately. The platinum Schottky contact detectors showed a higher charge collection at lower voltages, but would not be fully biased due to a breakdown of the internal potential prior to reaching full bias. Biasing at less than the full bias resulted in a less than total charge collection efficiency. Breakdown at a lower potential… Advisors/Committee Members: Blue, Thomas (Advisor).
Jarrell, Joshua Taylor. "High Temperature Characterization and Endurance Testing of Silicon Carbide Schottky Barrier Alpha Detectors." 2015. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1420467919.
Jarrell, Joshua Taylor. "High Temperature Characterization and Endurance Testing of Silicon Carbide Schottky Barrier Alpha Detectors." 2015. Web. 22 Apr 2019.
Jarrell JT. High Temperature Characterization and Endurance Testing of Silicon Carbide Schottky Barrier Alpha Detectors. [Internet] [Masters thesis]. The Ohio State University; 2015. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1420467919.
22. Petrie, Christian Matthew. Characterization of the Performance of Sapphire Optical Fiber in Intense Radiation Fields, when Subjected to Very High Temperatures.
▼ The U.S. Department of Energy is interested in extending optically-based instrumentation from non-extreme environments to extremely high temperature radiation environments for the purposes of developing in-pile instrumentation. The development of in-pile instrumentation would help support the ultimate goal of understanding the behavior and predicting the performance of nuclear fuel systems at a microstructural level. Single crystal sapphire optical fibers are a promising candidate for in-pile instrumentation due to the high melting temperature and radiation hardness of sapphire. In order to extend sapphire fiber-based optical instrumentation to high temperature radiation environments, the ability of sapphire fibers to adequately transmit light in such an environment must first be demonstrated. Broadband optical transmission measurements of sapphire optical fibers were made in-situ as the sapphire fibers were heated and/or irradiated. The damage processes in sapphire fibers were also modeled from the primary knock-on event from energetic neutrons to the resulting damage cascade in order to predict the formation of stable defects that ultimately determine the resulting change in optical properties.Sapphire optical fibers were shown to withstand temperatures as high as 1300 °C with minimal increases in optical attenuation. A broad absorption band was observed to grow over time without reaching a dynamic equilibrium when the sapphire fiber was heated at temperatures of 1400 °C and above. The growth of this absorption band limits the use of sapphire optical fibers, at least in air, to temperatures of 1300 °C and below. Irradiation of sapphire fibers with gamma rays caused saturation of a defect center located below 500 nm, and extending as far as ~1000 nm, with little effect on the transmission at 1300 and 1550 nm. Increasing temperature during gamma irradiation generally reduced the added attenuation.Reactor irradiation of sapphire fibers caused an initial rapid increase in attenuation, followed by a linear increase with continued irradiation time at constant reactor power. The linear increases were a result of displacement damage, and the rate of increase was proportional to the neutron flux. The transmission of sapphire fibers at 1300 and 1550 nm in a reactor radiation environment would ultimately be limited by the growth of low wavelength defect centers, whose tails extend into the near infrared. A model was proposed for the reactor radiation-induced attenuation that involves three previously reported color centers. The model accounts for gamma radiation-induced ionization of pre-existing defects, generation of new defects via displacement damage, and conversion between defect centers via ionization and charge recombination. Heated reactor irradiation experiments showed that the rate of increase of the added attenuation during constant power reactor irradiation monotonically decreases with increasing temperature up to 1000 °C, with the most significant decrease occurring between 300 and 600 °C. Testing of sapphire… Advisors/Committee Members: Blue, Thomas (Advisor).
Petrie, Christian Matthew. "Characterization of the Performance of Sapphire Optical Fiber in Intense Radiation Fields, when Subjected to Very High Temperatures." 2014. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1405011475.
Petrie, Christian Matthew. "Characterization of the Performance of Sapphire Optical Fiber in Intense Radiation Fields, when Subjected to Very High Temperatures." 2014. Web. 22 Apr 2019.
Petrie CM. Characterization of the Performance of Sapphire Optical Fiber in Intense Radiation Fields, when Subjected to Very High Temperatures. [Internet] [Doctoral dissertation]. The Ohio State University; 2014. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1405011475.
23. Flanders, Justin M. Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept.
▼ Surface power and nuclear electric propulsion in space necessitate the development of high energy density, long term continuous power sources. Research at The Ohio State University under the NASA Ralph Steckler Space Grant Colonization Research and Technology Development Opportunity has identified molten salt reactors (MSRs) as a potentially appealing technology for high power, high temperature space fission systems. This thesis examines component specific design related to thermal transport in an attempt to further establish the feasibility of MSRs in space. Specifically, the optimization of the associated heat exchangers for a Brayton power cycle is discussed in detail. In addition, power cycle and secondary coolant selection, material selection, and general MSR design considerations are discussed.The primary heat exchanger was optimized to maximize the margin to super prompt critical (MSPC), with a final MSPC equal to 513 pcm. The secondary and tertiary heat exchangers were optimized to minimize helium pressure drop, with a combined pressure loss of 2.62 kPa obtained. Advisors/Committee Members: Blue, Thomas (Advisor).
Flanders, Justin M. "Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept." 2012. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695.
Flanders, Justin M. "Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept." 2012. Web. 22 Apr 2019.
Flanders JM. Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695.
24. Goodenow, Debra A., B.S. Characterization of Effects of Mixed Neutron/Gamma Irradiation on NASA Glenn SiC Piezoresistive Pressure Sensors.
▼ SiC piezoresistive pressure sensors were developed by NASA Glenn Research Center GRC) for operation in high temperature environments. SiC's wide band gap and good radiation resistance make SiC piezoresistive pressure sensors potentially suitable for use in high radiation environments. In this thesis the degradation of SiC piezoresistive pressure sensors in a Wheatstone bridge configuration is evaluated in gamma and mixed neutron/gamma radiation fields. The performance of a Si piezoresistive pressure sensor in a Wheatstone bridge configuration was also evaluated in the same radiation fields for comparison. The degradation of the performance of the Si and SiC pressure sensors was evaluated by comparing the voltage response of the sensors to pressure before, during and after irradiation. There was noticeable degradation to the voltage response of the sensors. The change in the performance of the SiC pressure sensor due to radiation was compared to measurements of the effects of temperature on the sensor performance as determined by NASA GRC. The effect of radiation on the SiC sensor's performance was very similar to the effect of temperature on the SiC sensor's performance. Advisors/Committee Members: Blue, Thomas (Advisor).
Goodenow, Debra A., B S. "Characterization of Effects of Mixed Neutron/Gamma Irradiation on NASA Glenn SiC Piezoresistive Pressure Sensors." 2008. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1205356120.
Goodenow, Debra A., B S. "Characterization of Effects of Mixed Neutron/Gamma Irradiation on NASA Glenn SiC Piezoresistive Pressure Sensors." 2008. Web. 22 Apr 2019.
Goodenow, Debra A. BS. Characterization of Effects of Mixed Neutron/Gamma Irradiation on NASA Glenn SiC Piezoresistive Pressure Sensors. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1205356120.
25. Bratton, Isaac John. Modeling and Validation of the Fuel Depletion and Burnup of the OSU Research Reactor Using MCNPX/CINDER'90.
▼ The purpose of this study was to provide an accurate nuclide inventory, depletion and burnup of The Ohio State University Research Reactor (OSURR) Low Enriched Uranium (LEU) core using Monte Carlo techniques. This work will allow for a better understanding of the OSURR, thereby improving the risk-informed regulatory process, improving computer model predictive capability, and increasing understanding of the remaining fuel and reactor lifetime. This thesis used two separate methods for depletion analysis: a simple, relatively quick method, and a more detailed, computationally expensive method. The simple method calculated the consumption of 235U from the operational history and used a consumption rate of 1.23 g 235U /MWd. The depletion distribution was set proportional to the Monte Carlo N-Particle (MCNP) calculated fission reaction rate distribution. The second method tracked the evolution of all actinides and non-actinides produced using MCNPX and CINDER'90. MCNPX calculates the flux spectrum and reaction rates, which are then passed to CINDER'90 for depletion calculations and material nuclide inventory updates. Both methods used an updated MCNP model to track the depletion distribution throughout the OSURR core. The models were benchmarked against operational data from the reactor. The results of both methods were very comparable. The total 235U depletion, over the LEU core lifetime, was 65.83 grams and 66.61 grams for methods 1 and 2, respectively. It was found that approximately five grams of 239Pu was produced, contributing to the reactor fuel and power. Results showed that, while there was some variation of burnup between the fuel elements based on core position, the overall effect was negligible on effective fuel management of the core, and was well below burnup limits for structural integrity. The principal conclusion was that the fuel depletion is relatively small; however, due to the insertion of experimental facilities additional fuel assemblies have been added to maintain constant and sufficient excess reactivity. This thesis was an important step in initiating a fuel management program for the OSURR. In addition, the updated MCNP model of the OSURR will provide accurate calculations and better predictive capability of experimental results. The OSURR fuel management program will continue to follow core nuclide inventory. Future operation predictions can be used to predict core performance, fuel lifetime and optimize the core pattern. Advisors/Committee Members: Blue, Thomas (Advisor).
Bratton, Isaac John. "Modeling and Validation of the Fuel Depletion and Burnup of the OSU Research Reactor Using MCNPX/CINDER'90." 2012. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1343680610.
Bratton, Isaac John. "Modeling and Validation of the Fuel Depletion and Burnup of the OSU Research Reactor Using MCNPX/CINDER'90." 2012. Web. 22 Apr 2019.
Bratton IJ. Modeling and Validation of the Fuel Depletion and Burnup of the OSU Research Reactor Using MCNPX/CINDER'90. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1343680610.
26. Palmer, Robert K. Scaling of a Space Molten Salt Reactor Concept.
▼ The Space Molten Salt Reactor Concept considered for this study is a design for a 500 kW electric, 2 MW thermal liquid fueled molten salt reactor coupled to a Brayton power cycle to be used for Lunar or Martian surface power or for nuclear electric propulsion. To validate the concept, a scale terrestrial model would be built and tested. The goal of this work is to produce a design for a scale model or models that could be used to simulate the behavior of an actual reactor. Two scaling approaches were used. In the first approach, a laboratory-scale model was designed by focusing on power, cost, and safety. In the second approach, the model was scaled in order to achieve nearer similarity with the prototype. Advisors/Committee Members: Blue, Thomas (Advisor).
Palmer, Robert K. "Scaling of a Space Molten Salt Reactor Concept." 2015. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1437662933.
Palmer, Robert K. "Scaling of a Space Molten Salt Reactor Concept." 2015. Web. 22 Apr 2019.
Palmer RK. Scaling of a Space Molten Salt Reactor Concept. [Internet] [Masters thesis]. The Ohio State University; 2015. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1437662933.
27. Blake, Bryan P. Initial Testing of Single-Mode Optical Fibers Interrogated with an Optical Backscatter Reflectometer at High Temperatures and in Radiation Environments for Advanced Instrumentation in Nuclear Reactors.
▼ Although optical fibers have been used in the telecommunications industry for decades, the extreme temperature and radiation environments of next generation nuclear reactors has recently led to the exploration of optical fibers for advanced instrumentation and control. Optical fibers appear to be well suited for high temperature nuclear applications because they are immune to electromagnetic interference, can withstand harsh environments, and are capable of performing distributed sensing. Previous work with optical fibers has focused on the transmission of light. This thesis presents an alternative interferometric technique that measures the Rayleigh backscatter as a function of position using Luna Technologies' Optical Backscatter Reflectometer (OBR). The OBR has the capability to perform distributed temperature and strain sensing. However, this work investigated the optical backscattered signal as a function of position when the Corning SMF-28e+ single-mode optical fiber was exposed to high temperatures and radiation environments. The work has created a large set of OBR data that was analyzed to characterize single-mode fiber interrogated by the OBR at high temperatures and in radiation environments by monitoring the average fiber Amplitude (dB). Three experiments were performed: a 100 hour thermal-only experiment up to 1000°C, a 73 hour gamma irradiation experiment in the cobalt-60 irradiator at The Ohio State University Nuclear Reactor Laboratory up to 400°C, and a 450 hour reactor irradiation experiment at The Ohio State University Research Reactor up to 1000°C. This work has proven that optical amplitude measurements can be performed with the OBR at high temperatures in radiation environments. A temporary temperature effect was seen where the average fiber Amplitude (dB) increased with increasing temperature and decreased with decreasing temperature. Slight permanent damage was seen in the thermal-only and reactor irradiation experiments as a decrease in average fiber Amplitude (dB) due to high temperatures. The maximum decrease in average fiber Amplitude (dB) for the thermal-only and reactor irradiation experiments was less than 1 dB and 6 dB, respectively. Even at high temperatures in a reactor irradiation environment, light propagates to the heated and irradiated region of the test fiber and is scattered back with a large enough fraction to measure a signal that is distinguishable from the noise floor. As a next step, the experimental data acquired in these experiments will be analyzed with Luna Technologies' distributed sensing software to extract temperature information to determine if the OBR can function as a distributed sensor at high temperatures in radiation environments. Advisors/Committee Members: Blue, Thomas (Advisor).
Blake, Bryan P. "Initial Testing of Single-Mode Optical Fibers Interrogated with an Optical Backscatter Reflectometer at High Temperatures and in Radiation Environments for Advanced Instrumentation in Nuclear Reactors." 2012. Masters Thesis, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1344873713.
Blake, Bryan P. "Initial Testing of Single-Mode Optical Fibers Interrogated with an Optical Backscatter Reflectometer at High Temperatures and in Radiation Environments for Advanced Instrumentation in Nuclear Reactors." 2012. Web. 22 Apr 2019.
Blake BP. Initial Testing of Single-Mode Optical Fibers Interrogated with an Optical Backscatter Reflectometer at High Temperatures and in Radiation Environments for Advanced Instrumentation in Nuclear Reactors. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1344873713.
28. Reinke, Benjamin T. Cryogenic Irradiation and Low Temperature Annealing of Semiconductor and Optical Materials.
▼ A Cryogenic Irradiation Facility (CRIF) has been designed, fabricated, and tested for use in the pool of the Ohio State University Research Reactor (OSURR). This CRIF has supported in situ radiation induced damage experiments in optical and electronic materials at cryogenic temperatures and temperature controlled low temperature annealing experiments from cryogenic temperatures to above room temperature. The facility has been tested with liquid nitrogen and liquid helium out of the reactor pool. Temperature control has been demonstrated in the experimental volume of the CRIF from 4.2 K to above room temperature. The 10" Dry Tube, which will house the CRIF in the OSURR pool, has been inserted into OSURR pool and tested. The empty 10" Dry Tube and the CRIF have been simulated in a model of the OSURR using MCNP6 to understand the predicted radiation fields and total energy deposition in the empty 10" Dry Tube and in typical optical and electronic materials in the experimental volume of the CRIF. The radiation fields and the total radiation energy deposition have been used to predict experimental operating parameters for CRIF experiments, based upon desired dose calculations and time to boil-off for the liquid helium inside the CRIF. The CRIF has been used for four sets of experiments on single-mode and multi-mode silica optical fibers, in conjunction with a Luna Optics Optical Backscatter Reflectometer and an optical transmission measurement system, and on GaN High Electron Mobility Transistors, in conjunction with an integrated NI PXI Electronics Measurements System. These four experiments included (1) cryogenic materials characterization experiments without radiation, (2) gamma-only cryogenic irradiation experiments and low temperature annealing experiments, (3) reactor-on mixed field cryogenic irradiation experiments and low temperature annealing experiments, and (4) reactor-on mixed field room temperature irradiation experiments. These experiments were all completed at the OSU Nuclear Reactor Laboratory. The experiments demonstrated varying effects on the materials under test, depending on the temperature of the experiments and the radiation type, dose rate, and total dose of the experiments. The flexibility of the CRIF, in allowing for in situ measurements during cryogenic irradiation periods and during cooling/heating portions of the experiments, was shown to be vital in observing the complicated combined effects of the cryogenic irradiation. Advisors/Committee Members: Blue, Thomas (Advisor).
Reinke, Benjamin T. "Cryogenic Irradiation and Low Temperature Annealing of Semiconductor and Optical Materials." 2016. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1452250518.
Reinke, Benjamin T. "Cryogenic Irradiation and Low Temperature Annealing of Semiconductor and Optical Materials." 2016. Web. 22 Apr 2019.
Reinke BT. Cryogenic Irradiation and Low Temperature Annealing of Semiconductor and Optical Materials. [Internet] [Doctoral dissertation]. The Ohio State University; 2016. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1452250518.
29. Reisi Fard, Mehdi. The development of a high count rate neutron flux monitoring channel using silicon carbide semiconductor radiation detectors.
▼ In this dissertation, a fast neutron flux monitoring channel, which is based on the use of SiC semiconductor detectors is designed, modeled and experimentally evaluated as a power monitor for the Gas Turbine Modular Helium Reactors. A detailed mathematical model of the SiC diode detector and the electronic processing channel is developed using TRIM, MATLAB and PSpice simulation codes. The flux monitoring channel is tested at the OSU Research Reactor. The response of the SiC neutron-monitoring channel to neutrons is in close agreement to simulation results. Linearity of the channel response to thermal and fast neutron fluxes, pulse height spectrum of the channel, energy calibration of the channel and the detector degradation in a fast neutron flux are presented. Along with the model of the neutron monitoring channel, a Simulink model of the GT-MHR core has been developed to evaluate the power monitoring requirements for the GT-MHR that are most demanding for the SiC diode power monitoring system. The Simulink model is validated against a RELAP5 model of the GT-MHR. This dyanamic model is used to simulate reactor transients at the full power and at the start up, in order to identify the response time requirements of the GT-MHR. Based on the response time requirements that have been identified by the Simulink model and properties of the monitoring channel, several locations in the central reflector and the reactor cavity are identified to place the detector. The detector lifetime and dynamic range of the monitoring channel at the detector locations are calculated. The channel dynamic range in the GT-MHR central reflector covers four decades of the reactor power. However, the detector does not survive for a reactor refueling cycle in the central reflector. In the reactor cavity, the detector operates sufficiently long; however, the dynamic range of the channel is smaller than the dynamic range of the channel in the central reflector. Advisors/Committee Members: Blue, Thomas (Advisor).
Reisi Fard, Mehdi. "The development of a high count rate neutron flux monitoring channel using silicon carbide semiconductor radiation detectors." 2006. Doctoral Dissertation, The Ohio State University. Accessed April 22, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1149088480.
Reisi Fard, Mehdi. "The development of a high count rate neutron flux monitoring channel using silicon carbide semiconductor radiation detectors." 2006. Web. 22 Apr 2019.
Reisi Fard M. The development of a high count rate neutron flux monitoring channel using silicon carbide semiconductor radiation detectors. [Internet] [Doctoral dissertation]. The Ohio State University; 2006. [cited 2019 Apr 22]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1149088480.


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About CGG
Head Office in Freetown
8 King Street, Freetown, Sierra Leone
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Campaign for Good Governance (CGG) is a registered national non-government organisation (NGO) advocating for good governance in Sierra Leone. Leaders of the pro-democracy movement formed CGG in 1996 after the first multi-party elections in three decades.
CGG exists to increase citizen participation in governance through advocacy, capacity building and civic education in order to build a more informed civil populace and a democratic State.
CGG works with key partners including international NGOs and government departments such as the police to effectively deliver programs; and belongs to several associations and research communities. This strong network and a long history of successful campaigns have given CGG an excellent reputation as one of Sierra Leone's finest NGOs.
CGG'S Services to the Public
CGG specializes in issues of Decentralization and Local Governance, Democratic Participation, Corruption, Human Rights, Gender, Peace-building, Poverty Reduction Strategy, and Budgeting. CGG also has vast experience in conducting scientific research, opinion polls on developmental issues, and analysis of policies.
The organization offers consultancy services to other organizations, international development partners, the government and other relevant stakeholders in and out of the country. CGG can facilitate training sessions, conduct research, opinion poll and surveys for and with partners on developmental issues.
PhotoCGG has a furnished training centre at its office in Freetown. The centre is equipped with an air conditioner, projector (for power point presentation), four PC Dell computers, white board, flip chart stand, and chairs and desks to accommodate 30 (thirty) individuals.
As part of CGG's efforts to give individuals the opportunity to work in the development and advocacy arena, the organisation offers non- remunerated internships to university and college students and even graduates both nationally and internationally.
Spaces are limited and therefore not all those who apply will necessarily be offered a position.
Campaign for Good Governance (CGG) is a registered national non-government organization (NGO) advocating for good governance in Sierra Leone.
8 King Street
Freetown, Sierra Leone.
cgg@slcgg.org
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