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Articles 1 - 11 of 11
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Multi-Physics Design And Analyses Of Long Life Reactors For Lunar Outposts, Timothy M. Schriener
Multi-Physics Design And Analyses Of Long Life Reactors For Lunar Outposts, Timothy M. Schriener
Nuclear Engineering ETDs
Future human exploration of the solar system is likely to include establishing permanent outposts on the surface of the Moon. These outposts will require reliable sources of electrical power in the range of 10's to 100's of kWe to support exploration and resource utilization activities. This need is best met using nuclear reactor power systems which can operate steadily throughout the long ~27.3 day lunar rotational period, irrespective of location. Nuclear power systems can potentially open up the entire lunar surface for future exploration and development. Desirable features of nuclear power systems for the lunar surface include passive operation, the …
Experimental Studies Of The Chemical Effects Of Zinc-Bearing Materials Following A Loss-Of-Coolant Accident In A Pressurized Water Reactor, David Allan Pease
Experimental Studies Of The Chemical Effects Of Zinc-Bearing Materials Following A Loss-Of-Coolant Accident In A Pressurized Water Reactor, David Allan Pease
Nuclear Engineering ETDs
Generic Safety Issue-191 (GSI-191) was developed by the United States Nuclear Regulatory Commission (U.S. NRC) to assess the effect of debris loading on pressurized water reactor (PWR) emergency core cooling systems (ECCS) sump strainers during a Loss-of-Coolant Accident (LOCA). Potential contributors to the debris loading include latent dirt, fiberglass insulation, paints, epoxies, and chemical products which form when containment surfaces interact with the released reactor coolant. Chemical effects experiments have been completed to assess the potential debris loading contributions of zinc-bearing materials found in the containment building. Zinc-bearing materials in containment include galvanized steel and inorganic zinc-coated steel (IOZ). This …
Serpent Modeling Of The Transient Reactor Test Facility And Comparison With Measured Experimental Data, Joseph Templeton
Serpent Modeling Of The Transient Reactor Test Facility And Comparison With Measured Experimental Data, Joseph Templeton
Nuclear Engineering ETDs
Following the events at the Fukushima Daiichi nuclear power plant complex on March 11th 2011, there is an increased need for research into accident tolerant light water reactor fuels. In addition to the need for accident tolerant fuels testing there is a rising demand for clean renewable energy and the design of many generation IV reactors to fill the role which will require testing of such reactors and their fuels. Calculations and simulations are vital for the development and initial testing of these fuels, however ultimately experiments must be performed that push the fuels to the limits of their safety …
Ionization Chamber Design, Development, And Testing For The Unm Fission Fragment Spectrometer, Lena Heffern
Ionization Chamber Design, Development, And Testing For The Unm Fission Fragment Spectrometer, Lena Heffern
Nuclear Engineering ETDs
Fission fragment and product inventories play an important role in many areas of nuclear science from simulation of fissioning systems to active and passive interrogation of nuclear materials. The characteristic properties of fission fragment distributions are currently lacking in experimental data. New data is needed to reduce the uncertainty in the current standard data and to expand on current data for other incident neutron energies. To attain the goal of new fission fragment data, the Spectrometer for Ion Detection in Fission Research (SPIDER) project is currently underway at Los Alamos National Labortory (LANL). The SPIDER project is intended to be …
A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method With Implementation In Geant4, David Dixon
A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method With Implementation In Geant4, David Dixon
Nuclear Engineering ETDs
The subject of this dissertation is a moment-preserving Monte Carlo electron transport method that is more efficient than analog or detailed Monte Carlo simulations, yet provides accuracy that is statistically indistinguishable from the detailed simulation. Moreover, the Moment-Preserving (MP) method is formulated such that it is distinctly different than Condensed History (CH) methods making the MP method free of the limitations inherent to CH and proving a viable alternative for transporting electrons. Analog, or detailed, Monte Carlo simulations of charged particle transport is computationally intensive; thus, it is impractical for routine calculations. The computational cost of analog Monte Carlo is …
Space-Time Kinetics Of The Agn-201m Research Reactor At The University Of New Mexico, Douglas Bowen
Space-Time Kinetics Of The Agn-201m Research Reactor At The University Of New Mexico, Douglas Bowen
Nuclear Engineering ETDs
A series of experimental measurements were performed on the AGN- 201M reactor (AGN) at the University of New Mexico. Steady-state measurements were made with the AGN in various delayed critical configurations. These delayed critical configurations are defined by moving the coarse and fine control rods to unique positions in the core. These experiments also provided data for control rod integral and differential reactivity worth estimates. Thermal flux measurments taken radially in the glory hole region of the AGN reactor were also compiled for this work. A series of time-dependent experiments were performed in conjunction with the steady-state measurements that involved …
Identification Of Electrorefiner And Cathode Processing Failure Modes And Determination Of Signature-Significance For Integration Into A Signature Based Safeguards Framework For Pyroprocessing, Philip Lafreniere
Nuclear Engineering ETDs
The traditional method of safeguarding nuclear facilities, nuclear material accountancy (NMA), faces many challenges when applied to pyroprocessing facilities. To aid in the safeguarding of these facilities, process monitoring (PM) is being investigated as a complementary method to NMA. PM takes general process data, such as density, current etc., and applies it to safeguards through the use of a statistical framework. Signature Based Safeguards (SBS), a proposed statistical framework for the application of PM techniques, identifies anomalous scenarios and subsequently identifies and detects their respective PM signatures from a system of sensors. This work focuses both on assisting SBS through …
Characterization Of The Neutron Irradiation System For Use In The Low-Dose-Rate Irradiation Facility At Sandia National Laboratories, Jr. Manuel Franco
Characterization Of The Neutron Irradiation System For Use In The Low-Dose-Rate Irradiation Facility At Sandia National Laboratories, Jr. Manuel Franco
Nuclear Engineering ETDs
The objective of this work was to characterize the neutron irradiation system consisting of americium 241 beryllium (241AmBe) neutron sources placed in a polyethylene shielding for use at Sandia National Laboratories (SNL) Low Dose Rate Irradiation Facility (LDRIF). With a total activity of 0.3 TBq (9 Ci), the source consisted of three recycled 241AmBe sources of different activities that had been combined into a single source. The source in its polyethylene shielding will be used in neutron irradiation testing of components. The characterization of the source-shielding system was necessary to evaluate the radiation environment for future experiments. Characterization of the …
Predicting The Sensitivity Of A Beryllium/Scintillator Fusion Neutron Detector Combining Experimental Methods And Monte Carlo Models, Jedediah Styron
Predicting The Sensitivity Of A Beryllium/Scintillator Fusion Neutron Detector Combining Experimental Methods And Monte Carlo Models, Jedediah Styron
Nuclear Engineering ETDs
For this work a methodology has been developed to predict the sensitivity of a beryllium/scintillator fusion neutron detector. Neutrons may be captured by the beryllium via the 9Be (n, α) 6He nuclear reaction, where the product nucleus, 6He, decays by beta emission. The beta particles can be detected by close coupling scintillator with the beryllium. The methodology relates beta energy deposition to absolute measured scintillation light output as a function of detector bias, reflective material, scintillator thickness, and solid angle subtended by the scintillator on the face of the PMT. Output signals were measured from thin plastic scintillator using NIST …
Environmental Radiation Dose Assessment And Validation For Uranium Hexafluoride Storage Management, Shiaw-Der Su
Environmental Radiation Dose Assessment And Validation For Uranium Hexafluoride Storage Management, Shiaw-Der Su
Nuclear Engineering ETDs
This research entailed development and application of an efficient indirect Monte Carlo simulation methodology for performing environmental radiation dose assessment for storage of a large number (thousands) of uranium hexafluoride (UF6) cylinders in an outdoor storage area. The primary objective was to substantially improve the Monte Carlo computational efficiency by an order of magnitude or better as compared to the previous time-consuming methodology using the direct, standard simulation approach. The collateral objective was to support onsite storage of UF6 cylinders at uranium enrichment facilities, addressing dose impacts on storage capacity, footprint requirements, and cylinder placement in terms of spacing, array …
Validation Studies Of Single-Phase Natural Circulation Response Of The Fluoride Salt-Cooled High-Temperature Reactor (Fhr), Amy Drumm
Nuclear Engineering ETDs
The purpose of this work was to develop and validate a design tool for the transients that are of interest in designing the decay heat removal system for a Fluoride salt-cooled High-temperature Reactor (FHR). The loop of interest operates with a single phase, near ambient pressure molten salt coolant. Most of the codes used for LWR safety and licensing were designed to model more complex heat transfer problems. A single phase, one dimensional, natural circulation code is more suited to validating with simple university experiments. A code designed for lead bismuth eutectic at the Bhabha Atomic Research Centre (BARC) was …