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Effects of burnup on fuel failure. Power burst tests on fuel rods with 13,000 and 32,000 MWd/MTU burnup

Description: Results are presented from preliminary tests designed to investigate the behavior of preirradiated fuel rods under reactivity initiated accident (RIA) conditions. The tests were conducted in 1970 as part of the SPERT/Capsule Driver Core (CDC) program. The report was intended to be published in a series of Idaho Nuclear Corporation Interim Technical Reports (IN-ITRs); however, the CDC program was terminated before the report could be released. In September 1975, the Nuclear Regulatory Commission concluded that the data contained in the report could be a valuable reference in planning future water reactor safety program tests and requested its release.
Date: January 1, 1976
Creator: Miller, R.W.
Partner: UNT Libraries Government Documents Department

Monte Carlo simulation of neutral beam injection into fusion reactors

Description: Motivations and techniques for the Monte Carlo computer simulation of energetic neutral beam injection for fusion reactors are described. The versatility of this approach allows a significantly more sophisticated treatment of charge transfer collision phenomena and consequent effects on engineering design than available from prior work. Exemplary results for a mirror Fusion Engineering Research Facility (FERF) are discussed. (auth)
Date: September 15, 1975
Creator: Miller, R.L.
Partner: UNT Libraries Government Documents Department

DIE Deflection Modeling: Empirical Validation and Tech Transfer

Description: This report summarizes computer modeling work that was designed to help understand how the die casting die and machine contribute to parting plane separation during operation. Techniques developed in earlier research (8) were applied to complete a large computational experiment that systematically explored the relationship between the stiffness of the machine platens and key dimensional and structural variables (platen area covered, die thickness, platen thickness, thickness of insert and the location of the die with respect to the platen) describing the die/machine system. The results consistently show that there are many significant interactions among the variables and it is the interactions, more than the individual variables themselves, which determine the performance of the machine/die system. That said, the results consistently show that it is the stiffness of the machine platens that has the largest single impact on die separation.
Date: May 28, 2003
Creator: Miller, R. Allen
Partner: UNT Libraries Government Documents Department

Modeling the Mechanical Performance of Die Casting Dies

Description: The following report covers work performed at Ohio State on modeling the mechanical performance of dies. The focus of the project was development and particularly verification of finite element techniques used to model and predict displacements and stresses in die casting dies. The work entails a major case study performed with and industrial partner on a production die and laboratory experiments performed at Ohio State.
Date: February 27, 2004
Creator: Miller, R. Allen
Partner: UNT Libraries Government Documents Department

Synthesis of New Water-Soluble Metal-Binding Polymers combinatorial Chemistry Approach

Description: (1) Synthesis of Fused Tetraheterocyclic Azepines: (2) Synthesis of Linear Bidentate Diisoxazole and Bidentate Isoxazole-Furyl/Thienyl/Pyridyl Motifs: (3) Synthesis of Pyrazolo[3,4-g] [2,1] dihydrobenzoisoxazol(in)es: (4) Synthesis of Spiro-Fused (C5)-Isozazoline-(C4)-Pyrazolones:
Date: May 7, 2004
Creator: Miller, R. Bryan
Partner: UNT Libraries Government Documents Department

Development of a Software Framework for System-Level Carbon Sequestration Risk Assessment

Description: The overall purpose of this project was to identify, evaluate, select, develop, and test a suite of enhancements to the GoldSim software program, in order to make it a better tool for use in support of Carbon Capture and Sequestration (CCS) projects. The GoldSim software is a foundational tool used by scientists at NETL and at other laboratories and research institutions to evaluate system-level risks of proposed CCS projects. The primary product of the project was a series of successively improved versions of the GoldSim software, supported by an extensive User’s Guide. All of the enhancements were tested by scientists at Los Alamos National Laboratory, and several of the enhancements have already been incorporated into the CO{sub 2}-PENS sequestration model.
Date: February 28, 2013
Creator: Miller, R.
Partner: UNT Libraries Government Documents Department

Production Tests-240: Gamma spectrometer development and testing

Description: The office of Safeguards and Nuclear Materials Management of the US Atomic Energy Commission has commissioned Battelle-Northwest to design, build, and test a gamma spectrometer with the specific purpose of measuring photo peaks emitted from irradiated fuel. The parameters of interest are not just the photo peaks but the variations of the rays with respect to irradiation time in the reactor and storage time after discharge from the reactor. The spectrometer is being built at Tech Shops in the 300 Area and is scheduled to be installed in the cobalt irradiation facility of the KE Reactor spent fuel storage basin during the first week of November, 1970. One complete tube of 38 natural uranium fuel elements, irradiated at KE Reactor, will be specifically discharged for this test program and will be scanned at weekly intervals for a period of one year following the date of discharge by Battelle-Northwest technicians using the spectrometer in the fuel basin. This production test defines the number of fuel assemblies required, the exposure criteria for the fuel, and the special handling procedure necessary to maintain identification of the fuel from the time of discharge. The objective of this test is to invent a system of gamma-ray measurements which can be used to derive the exposure and time after discharge of spent reactor fuel.
Date: September 30, 1979
Creator: Miller, R.L.
Partner: UNT Libraries Government Documents Department

Understanding the Relationship Between Filling Pattern and Part Quality in Die Casting

Description: The overall objective of this research project was to investigate phenomena involved in the filling of die cavities with molten alloy in the cold chamber die-casting process. It has long been recognized that the filling pattern of molten metal entering a die cavity influences the quality of die-cast parts. Filling pattern may be described as the progression of molten metal filling the die cavity geometry as a function of time. The location, size and geometric configuration of points of metal entry (gates), as well as the geometry of the casting cavity itself, have great influence on filling patterns. Knowledge of the anticipated filling patterns in die-castings is important for designers. Locating gates to avoid undesirable flow patterns that may entrap air in the casting is critical to casting quality - as locating vents to allow air to escape from the cavity (last places to fill). Casting quality attributes that are commonly flow related are non-fills, poor surface finish, internal porosity due to trapped air, cold shuts, cold laps, flow lines, casting skin delamination (flaking), and blistering during thermal treatment.
Date: March 15, 2004
Creator: Brevick, Jerald & Miller, R. Allen
Partner: UNT Libraries Government Documents Department

Removal of silica from Raft River geothermal water

Description: Lack of sufficient quantities of clean surface or near-surface water at Raft River for cooling purposes dictates that cooled geothermal fluid, effluent from the Raft River 5 MW(e) Pilot Power Plant, must also be used as condenser coolant. Prior testing revealed that a water-treatment system would be required to reduce silica and calcium concentrations of the cooling fluid. The water-treatment system specified was to use dolomitic lime for both pH adjustment and source of magnesium. The dolomitic lime treatment was investigated and found to be inadequate. Subsequent testing was done to find chemical systems that would adequately reduce silica concentrations. Three magnesium and two iron compounds were found which reduced silica to acceptable concentration levels. They are magnesium bicarbonate, magnesium chloride, magnesium sulfate, iron sulfate, and iron chloride. Magnesium oxide, using a two-stage countercurrent process, will also reduce silica to adequate levels.
Date: June 1, 1980
Creator: Suciu, D.F. & Miller, R.L.
Partner: UNT Libraries Government Documents Department

Use of hodoscopes at ISABELLE

Description: A major problem for experimenters designing detectors for use at ISABELLE is the high interaction rate, one event every 25 nanoseconds at a luminosity of 10/sup 33/ cm/sup -2/ sec/sup -1/. Typical multiplicities range from a few at large angles (> approximately 45/sup 0/) to approximately 10 nearer the forward direction. This implies average rates as high as a particle every few nanoseconds. For experiments which require high luminosities, detectors must be designed which have very short (approximately 1 nsec) response time and/or intercept a small solid angle per element. These requirements are met by fine-grained scintillation counter hodoscopes. However, it is, at present, impractical to maintain a 10,000 element hodoscope array because of the difficulty of light piping, the complexity and expense of maintaining that many phototubes, and the problems of packaging and readout. Several developments which promise to make such large arrays feasible are discussed.
Date: January 1, 1977
Creator: Alspector, J. & Miller, R.J.
Partner: UNT Libraries Government Documents Department

SPERT I DESTRUCTIVE TEST PROGRAM SAFETY ANALYSIS REPORT

Description: The water-moderated core used for destructive experiments is mounted in the Spent I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is an array of highly enriched aluminum clad, plate-type fuel assemblies, using four bladetype, gang-operated control rods. Reactor transients are initiated at ambient temperature by step-insentions of reactivity, using a control rod which can be quickly ejected from the core. Following an initial series of static measurements to determine the basic- reactor properties of the test core, a series of nondestructive, self-limiting power excursion tests was performed, which covered a reactor period range down to the point where minor fuel plate damage first occurred -approximately for a 10- msec period test. These tests provided power, temperature, and pressure data. Additional kinetic teste in the period region between 10 and 5 msec were completed to explore the region of limited core damage. Fuel plate damage results included plate distortion, cladding cracking, and fuel melting. These exploratory tests were valuable in revealing unexpected changes in the dependence of pressure, temperature, burst energy, and burst shape parameters on reactor period, although the dependence of peak power on reactor period was not significantly changed. An evaluation of hazards involved in conducting the 2- msec test, based on pessimistic assumptions regarding fission product release and weather conditions, indicates that with the procedural controls normally exercised in the conduct of any transient test at Spent and the special controls to be in effect during the destructive test series, no significant hazard to personnel or to the general public will be obtained. All nuclear operation is conducted remotely approximately 1/2 mile from the reactor building. Discussion is also given of the supervision and control of personnel during and after each destructive test, and of the plans for re-entry, cleanup, ...
Date: June 15, 1962
Creator: Spano, A.H. & Miller, R.W.
Partner: UNT Libraries Government Documents Department

Effects of Remote Drop and Pumpdown Placement on Cellular Concrete

Description: Abstract: The hazards to the public posed by abandoned mine shafts are well documented. As private development encroaches on previously mined areas, the potential for fatalities and serious injuries from abandoned mine shafts increases. The U.S. Bureau of Mines has conducted research into cellular concrete as a material for sealing these openings. The current work involves testing the characteristics of cellular concrete before and after it had been pumped or dropped from different heights into a simulated mine shaft. Cellular concrete was pumped vertically up to and subsequently dropped from heights of 18 and 37 m into concrete forms. Wet density measurements were made at multiple sampling points in the test circuit. Air content determinations and uniaxial compressive strength testing were conducted. Research results showed significant loss in air content and changes in the characteristics of cellular concrete during pumping or dropping from various heights. Recommendations on effective use of cellular concrete for sealing abandoned mine shafts are made.
Date: 1995
Creator: Boreck, D. L. & Miller, R. E.
Partner: UNT Libraries Government Documents Department

Emittance Dilution due to Dipole Mode Rotating and Coupling in the Main Linacs of the ILC

Description: The progress of multiple bunches of charged particles down the main L-band linacs of the ILC (International Linear Collider) can be disrupted by wakefields. These wakefields correspond to the electromagnetic fields excited in the accelerating cavities and have both long-range and short-range components. The horizontal and vertical modal components of the wakefield will be excited at slightly different frequencies (the dipole mode frequency degeneracy's are split) due to inevitable manufacturing errors. We simulate the progress of the ILC beam down the collider under the influence of these wakefields. In particular, we investigate the consequences on the final emittance dilution of the beam of coupling of the horizontal to the vertical motion of the beam.
Date: May 25, 2005
Creator: Jones, R. M. & Miller, R. H.
Partner: UNT Libraries Government Documents Department

Helium-Bearing Natural Gases of the United States: Analyses, Second Supplement to Bulletin 486

Description: Supplementary report from the U.S. Bureau of Mines regarding the results of a survey of the natural gas (helium) resources available in the United States. From the summary: "Results of analyses by the Bureau of Mines of 1,444 samples from oil and gas wells and natural gas pipelines collected from 23 states are presented in the Bulletin in tabular form. The information is from samples collected in the period May 1956 to January 1961 and supplements earlier publications" (p. 1). The summary also notes that the samples include several new sources in Arizona, Colorado, New Mexico, and Utah, which were discovered after May 1956 and found to be unlike the samples from previous reports.
Date: 1963
Creator: Munnerlyn, R. D. & Miller, R. D.
Partner: UNT Libraries Government Documents Department

Qualitative Reasoning for Additional Die Casting Applications

Description: If manufacturing incompatibility of a product can be evaluated at the early product design stage, the designers can modify their design to reduce the effect of potential manufacturing problems. This will result in fewer manufacturing problems, less redsign, less expensive tooling, lower cost, better quality, and shorter development time. For a given design, geometric reasoning can predict qualitatively the behaviors of a physical manufacturing process by representing and reasoning with incomplete knowledge of the physical phenomena. It integrates a design with manufacturing processes to help designers simultaneously consider design goals and manufacturing constraints during the early design stage. The geometric reasoning approach can encourage design engineers to qualitatively evaluate the compatibility of their design with manufacturing limitations and requirements.
Date: May 28, 2003
Creator: Miller, R. Allen; Cui, Dehua & Ma, Yuming
Partner: UNT Libraries Government Documents Department