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Design and fabrication of high density uranium dispersion fuels

Description: Twelve different uranium alloys and compounds with uranium densities greater than 13.8 g/cc were fabricated into fuel plates. Sixty-four experimental fuel plates, referred to as microplates, with overall dimensions of 76.2 mm x 22.2 mm x 1.3 mm and elliptical fuel zone of nominal dimensions of 51 mm x 9.5 mm, began irradiation in the Advanced Test Reactor on August 23, 1997. The fuel test matrix consists of machined or comminuted (compositions are in weight %) U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb… more
Date: November 1, 1997
Creator: Trybus, C. L.; Meyer, M. K.; Clark, C. R.; Wlencek, T. C. & McGann, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department

[Andrea Robledo and guest at 2004 La Raza event]

Description: A photograph of Andrea Robledo and a guest seated at the 2004 Fall Multicultural Center's La Raza Graduation event. They are at one of the banquet tables and there are other tables behind them. They also have food and drinks in front of them.
Date: October 21, 2004
Creator: University of North Texas. Multicultural Center.
Item Type: Refine your search to only Photograph
Partner: UNT Libraries Special Collections
open access

[News Script: Beef]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, relating a news story of the high price of beef which has hit the department of agriculture.
Date: 1973-08-23T24:00:00
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections

[Photograph of a woman giving a speech]

Description: Photograph of a woman wearing a beret standing and giving a speech. The table in front of her is covered in a white table cloth along with various dishes, including carafes, glasses, plates, cutlery, and salt and pepper shakers, and cups. Several people are sitting to each of her sides, one of whom is smoking a cigarette.
Date: [1939..1989]
Creator: Clark, Joe
Item Type: Refine your search to only Photograph
Partner: UNT Libraries Special Collections
open access

Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Weld Penetration and Defect Control

Description: Highly engineered designs increasingly require the use of improved materials and sophisticated manufacturing techniques. To obtain optimal performance from these engineered products, improved weld properties and joint reliability are a necessarily. This requirement for improved weld performance and reliability has led to the development of high-performance welding systems in which pre-programmed parameters are specified before any welding takes place. These automated systems however lack the ab… more
Date: May 15, 1992
Creator: Chin, Bryan A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of multidimensional calculations of long-rod impacts on oblique plates

Description: The justification for three-dimensional versus two-dimensional simulations of non-symmetric armor penetration problems has been a topic of discussion for many years. Two-dimensional plane-strain approximations are generally not quantitatively accurate, especially at later times, but they can be performed efficiently and the results are usually acceptable. Although three-dimensional calculations provide better results, they are very time consuming and expensive to perform. But with the improved … more
Date: January 1, 1989
Creator: Fujita, R.K. & Cort, G.E. (Los Alamos National Lab., NM (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Beryllium Use in the Advanced Test Reactor

Description: The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) began operation in 1967. It makes use of a unique serpentine fuel core design and a beryllium reflector. Reactor control is achieved with rotating beryllium cylinders to which have been fastened plates of hafnium. Over time, the beryllium develops rather high helium content because of nuclear transmutations and begins to swell. The beryllium must be replaced at nominally 10-year intervals. Determination of when the replaceme… more
Date: December 1, 2007
Creator: Longhurst, Glen R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Validating MCNP for LEU Fuel Design via Power Distribution Comparisons

Description: The mission of the Reduced Enrichment for Research and Test Reactors (RERTR) Program is to minimize and, to the extent possible, eliminate the use of highly enriched uranium (HEU) in civilian nuclear applications by working to convert research and test reactors, as well as radioisotope production processes, to low enriched uranium (LEU) fuel and targets. Oak Ridge National Lab (ORNL) is reviewing the design bases and key operating criteria including fuel operating parameters, enrichment-related… more
Date: November 1, 2008
Creator: Primm, Trent; Maldonado, G Ivan & Chandler, David
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Copyright laws]

Description: Video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story.
Date: May 10, 1978, 6:00 p.m.
Duration: 2 minutes 24 seconds
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
open access

Evaluations of the Irwin. beta. /sub Ic/ adjustment for small specimen fracture toughness data

Description: When small specimens are used to measure the cleavage fracture toughness of pressure vessel steels in the transition range of temperature, specimen thickness size effects and large amounts of data scatter are often observed. The size effects are manifested by an increase in the average value of fracture toughness with decreasing specimen thickness, eventually resulting in a change in fracture mode from cleavage to ductile tearing. It has been shown that a semiempirical adjustment for the intera… more
Date: January 1, 1983
Creator: Merkle, J.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

Description: The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the… more
Date: July 1, 1993
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The Meta-Lax method of stress reduction in welds. [ASTM A36; AISI 4140]

Description: This study is the second phase of ongoing research into the mechanics and feasibility of using the Meta-Lax method of vibratory stress relief in place of thermal methods of stress relief. The first phase of this research revealed results that were similar to, and even superior to those achieved using thermal methods. The testing here was designed to eliminate the effects of interbead tempering by utilizing single pass bead-on-plate welds only. A metallurgical explanation for the success of the … more
Date: July 31, 1992
Creator: Smith, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A computer model for the transient analysis of compact research reactors with plate type fuel

Description: A coupled neutronics and core thermal-hydraulic performance model has been developed for the analysis of plate type U-Al fueled high-flux research reactor transients. The model includes point neutron kinetics, one-dimensional, non-homogeneous, equilibrium two-phase flow and beat transfer with provision for subcooled boiling, and spatially averaged one-dimensional beat conduction. The feedback from core regions other than the fuel elements is included by employing a lumped parameter approach. Pa… more
Date: March 1, 1994
Creator: Sofu, T. & Dodds, H. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

CRDIAC: Coupled Reactor Depletion Instrument with Automated Control

Description: When modeling the behavior of a nuclear reactor over time, it is important to understand how the isotopes in the reactor will change, or transmute, over that time. This is especially important in the reactor fuel itself. Many nuclear physics modeling codes model how particles interact in the system, but do not model this over time. Thus, another code is used in conjunction with the nuclear physics code to accomplish this. In our code, Monte Carlo N-Particle (MCNP) codes and the Multi Reactor Tr… more
Date: August 1, 2012
Creator: Logan, Steven K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

X-Ray Diffraction Project Final Report, Fiscal Year 2006

Description: An x-ray diffraction diagnostic system was developed for determining real-time shock-driven lattice parameter shifts in single crystals at the gas gun at TA-IV at Sandia National Laboratories (SNL). The signal-to-noise ratio and resolution of the system were measured using imaging plates as the detector and by varying the slit width. This report includes tests of the x-ray diffraction system using a phosphor coupled to a charge-coupled device (CCD) camera by a coherent fiber-optic bundle. The s… more
Date: October 1, 2006
Creator: Morgan, Dane V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Characterization and Testing of Monolithic RERTR Fuel Plates

Description: Monolithic fuel plates are being developed for application in research reactors throughout the world. These fuel plates are comprised of a U-Mo alloy foil encased in aluminum alloy cladding. Three different fabrication techniques have been looked at for producing monolithic fuel plates: hot isostatic pressing (HIP), transient liquid phase bonding (TLPB), and friction stir welding (FSW). Of these three techniques, HIP and FSW are currently being emphasized. As part of the development of these fa… more
Date: March 1, 2007
Creator: Keiser, D. D.; Jue, J. F. & Burkes, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Determination of Neptunium-237 in Human Urine

Description: A method has been developed for determining neptunium -237 in human urine specimens. The urine is acidified, then concentrated by evaporation. Uranium is removed by a double lanthanum fluoride precipitation using ferrous ammonium sulfate and hydroxylamine hydrchloride as reducing agents. Separation from plutonium is effected by a thenoyltrifluoroacetone extraction using potassium iodide-hydrazine or potassium iodide-hydroxylamine to reduce plutonium to Pub$sup +3$ and neptunium to Np$sup +4$. T… more
Date: June 1, 1964
Creator: Miller, J. A. & Biggerstaff, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Kodak, Jr. No. 2C Autographic camera closed]

Description: Photograph of an antique Kodak, Jr. No. 2C Autographic camera. The camera is lying on its side and the front covering, which also functions as a platform for the bellows, is almost closed. This leaves the interior of the camera covered, but the "Kodak" nameplate is visible.
Date: December 4, 2013
Creator: Sylve, Joshua
Item Type: Refine your search to only Photograph
Location: 33.210113 -97.148993
Partner: UNT Libraries Special Collections
open access

A Review of X-ray Diagnostic Calibrations in the 2 to 100 keV Region Using the High Energy X-ray Calibration Facility (HEX)

Description: The precise and accurate measurement of X-rays in the 2 keV to 100 keV region is crucial to the understanding of HED plasmas and warm dense matter in general. With the emergence of inertially confined plasma facilities as the premier platforms for ICF, laboratory astrophysics, and national security related plasma experiments, the need to calibrate diagnostics in the high energy X-ray regime has grown. At National Security Technologies High Energy X-ray Calibration Facility (HEX) in Livermore, C… more
Date: May 19, 2010
Creator: Ali, Zaheer; Pond, T.; Buckles, R. A.; Maddox, B. R.; Chen, C. D.; DeWald, E. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

PARFUME User's Guide

Description: PARFUME, a fuel performance analysis and modeling code, is being developed at the Idaho National Laboratory for evaluating gas reactor coated particle fuel assemblies for prismatic, pebble bed, and plate type fuel geometries. The code is an integrated mechanistic analysis tool that evaluates the thermal, mechanical, and physico-chemical behavior of coated fuel particles (TRISO) and the probability for fuel failure given the particle-to-particle statistical variations in physical dimensions and … more
Date: September 1, 2010
Creator: Hamman, Kurt
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ZPR-3 Assembly 11 : A cylindrical sssembly of highly enriched uranium and depleted uranium with an average {sup 235}U enrichment of 12 atom % and a depleted uranium reflector.

Description: Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR crit… more
Date: September 30, 2010
Creator: Lell, R. M.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Security, National & Engineering, Inst. of Physics and Power
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ZPR-3 Assembly 6f : A Spherical Assembly of Highly Enriched Uranium, Depleted Uranium, Aluminum and Steel With an Average {Sup 235}U Enrichment of 47 Atom %.

Description: Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR crit… more
Date: September 30, 2010
Creator: Lell, R. M.; McKnight, R. D; Schaefer, R. W. & Division, Nuclear Engineering
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of Borax Experiments

Description: An analysis of the self-limitation of power excursions by steam production in heterogeneous water-moderated reactors using MTR- type fuel elements seems to give excellent agreement with Borax data on both fuel plate temperature rise and total energy for excursions in which the reactor is initially at saturation temperature. A simple model for steam production is developed from thermodynamic and heat diffusion considerations. In those cases for which the reactor is substantially sub-cooled, it a… more
Date: January 1, 1955
Creator: Edlund, M.C. & Noderer, L.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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