Kilowatt Isotope Power System: component report for the Ground Demonstration System Accumulator (open access)

Kilowatt Isotope Power System: component report for the Ground Demonstration System Accumulator

The Model Number ORC1A3A01 System Accumulator for the Kilowatt Isotope Power System was expulsion tested and demonstrated to be in compliance with the requirements of Sundstrand Explusion Test Procedure, TP 400. Test requirements of TP 400 were extracted from the Kilowatt Isotope Power System, Ground Demonstration System Test Plan.
Date: January 31, 1978
Creator: Brainard, E.L.
Object Type: Report
System: The UNT Digital Library
Homogenization of arc-melted uranium-6 weight percent niobium alloy ingots (open access)

Homogenization of arc-melted uranium-6 weight percent niobium alloy ingots

Microsegregation and macrosegregation in uranium-6 niobium arc-melted ingots were characterized by electron microprobe analysis. Homogenization studies determined that microsegregation can be eliminated by heat treating the alloy for six hours at 1100/sup 0/C. Extensive homogenization did not eliminate macrosegregation (banding) from the as-cast alloy, but a mathematical model describing banding and coring indicated that banding could possibly be eliminated by working prior to homogenization.
Date: January 31, 1978
Creator: Snyder, W. B., Jr.
Object Type: Report
System: The UNT Digital Library
Evaluation of ultrafiltration membranes for treating low-level radioactive contaminated liquid waste (open access)

Evaluation of ultrafiltration membranes for treating low-level radioactive contaminated liquid waste

A series of experiments were performed on Waste Disposal Facility (WD) influent using Romicon hollow fiber ultrafiltration modules with molecular weight cutoffs ranging from 2000 to 80,000. The rejection of conductivity was low in most cases. The rejection of radioactivity ranged from 90 to 98%, depending on the membrane type and on the feed concentration. Typical product activity ranged from 7 to 100 dis/min/ml of alpha radiation. Experiments were also performed on alpha-contaminated laundry wastewater. Results ranged from 98 to >99.8%, depending on the membrane type. This yielded a product concentration of less than 0.1 dis/min/ml of alpha radiation. Tests on PP-Building decontamination water yielded rejections of 85 to 88% alpha radiation depending on the membrane type. These experiments show that the ability to remove radioactivity by membrane is a function of the contents of the waste stream because the radioactivity in the wastewater is in various forms: ionic, polymeric, colloidal, and absorbed onto suspended solids. Although removal of suspended or colloidal material is very high, removal of ionic material is not as effective. Alpha-contaminated laundry wastewater proved to be the easiest to decontaminate, whereas the low-level PP-Building decontamination water proved to be the most difficult to decontaminate. Decontamination of …
Date: March 31, 1978
Creator: Koenst, J.W. & Roberts, R.C.
Object Type: Report
System: The UNT Digital Library
Apparatus for simultaneously measuring electrical conductivity and oxygen fugacity (open access)

Apparatus for simultaneously measuring electrical conductivity and oxygen fugacity

Electrical conductivity studies of silicates are useful in determining temperature vs depth in the earth. Realistic laboratory measurements of conduction mechanisms require that exact determinations of oxygen fugacity (fo{sub 2}) be made in the experimental environment. An apparatus is described that monitors system fo{sub 2} with a calcia-doped zirconia-oxygen cell while measuring electrical conductivity of iron-bearing silicates at high temperature (greater than 1000 K). The fo{sub 2} calculated thermodynamically from CO/CO{sub 2} mixing ratios agreed well with measurements made with the zirconia cell at 1473 K, except for fo{sub 2} greater than 10{sup -4} Pa, where, on a log{sub 10} scale, mixing-ratio errors were as large as +- 0.2. These errors are attributed to oxygen contamination in the CO{sub 2} and to mobile carbon deposits that formed in the apparatus.
Date: January 31, 1978
Creator: Netherton, R. & Duba, A.
Object Type: Report
System: The UNT Digital Library
Helium generation in fusion reactor materials. Technical progress report, April--September 1977 (open access)

Helium generation in fusion reactor materials. Technical progress report, April--September 1977

The near-term objectives of this program are to measure the spectrum-integrated helium generation rates and cross sections of a number of pure elements and alloys in several high-intensity neutron sources, and to develop and demonstrate neutron dosimetry procedures using some of these materials. To this end, four neutron irradiation experiments have now been run: one using accelerator-produced d-Be neutrons, two using the accelerator-produced d-T reaction, and one in the neutron field of a mixed-spectrum fission reactor. All of these irradiations have incorporated a large number of helium-generation materials.
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
System for vacuum pouring of epoxy tensile and impact specimens with a study of the behavior of these specimens at 77 K and 293 K (open access)

System for vacuum pouring of epoxy tensile and impact specimens with a study of the behavior of these specimens at 77 K and 293 K

The purpose of the investigation was to establish a suitable technique for vacuum pouring of epoxy test specimens and to study the behavior of these specimens at 77 K and 293 K. A series of tensile and impact tests was conducted using specimens made from the following resins: Epon 828, Epon 871, and Epon curing agent Z. These materials are of general interest to designers of magnets for cryogenic service. Tests of the specimens were carried out at 77 K and 293 K. The 77 K data indicate that tensile strength increases proportionally with the increase of Epon 871 relative to Epon 828. When the mixture includes more than 90% Epon 871, impact testing at 293 K becomes practically impossible due to the rubbery condition of the material. However, when tested at 77 K, this same mixture evinces high tensile strength. When optimum data are sought over a wide range of temperatures, 77 K to 293 K, it appears that a mixture of 70% Epon 871, 30% Epon 828 with 13 pph of curing agent Z or 50% Epon 871, 50% Epon 828 with 15 pph curing agent Z offers the best compromise in tensile strength, modulus of elasticity, and …
Date: March 31, 1978
Creator: Fitzpatrick, C.M. & Stoddart, W.C.T.
Object Type: Report
System: The UNT Digital Library
Beneficial uses of nuclear fission wastes (open access)

Beneficial uses of nuclear fission wastes

Sandia is investigating the use of /sup 137/Cs from radioactive waste to reduce the pathogen levels of municipal sewage sludges so that they can be used in agriculture, either as fertilizer or as feed supplement. The Sandia Irradiator for Dried Sewage Solids (SIDSS) is a pilot plant for treating 16 tons per day to a dose of 500 krad, using 1 MCi of /sup 137/Cs. A larger (25 ton/day) demonstration plant is also planned. A cost/benefit study of this application was made. Use of /sup 99/Tc for marine bifouling and corrosion inhibition is also being investigated. (DLC)
Date: March 31, 1978
Creator: Sivinski, H.D.
Object Type: Report
System: The UNT Digital Library
Laser-generated shock-wave experiments in metals above 1 TPa (open access)

Laser-generated shock-wave experiments in metals above 1 TPa

Some initial experiments are described which form part of a new program aimed at significantly extending the range of high pressures and densities which may be explored in laboratory equation-of-state (EOS) experiments. These experiments will utilize high-energy lasers, such as those employed in the Laser Fusion Program at Lawrence Livermore Laboratory (LLL), to generate intense shock waves in materials of interest.
Date: January 31, 1978
Creator: Trainor, R. J.; Shaner, J. W.; Auerbach, J. M. & Phillion, D. W.
Object Type: Article
System: The UNT Digital Library
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3. GSFLS technical and financial analysis. Interim report (open access)

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3. GSFLS technical and financial analysis. Interim report

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported herein. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports …
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Baseline Gas Turbine Development Program. Twenty-Third Combined Quarterly Progress Report, May 1, 1978--January 31, 1979 (open access)

Baseline Gas Turbine Development Program. Twenty-Third Combined Quarterly Progress Report, May 1, 1978--January 31, 1979

Progress is reported for a program whose goals are to demonstrate an experimental Upgraded gas turbine-powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine-powered, compact-size American automobile. This is the concluding progress report for this program; it covers the period from May 1, 1978 to January 31, 1979. The next formal report will be the final report, which is currently in process. Activity during this reporting period has continued to emphasize development towards correcting a power deficiency in the Upgraded Engine. Efforts are also being directed towards reducing fuel usage through improved heat recovery and towards improving the mechanical reliability and control of the engine.
Date: December 31, 1978
Creator: Pampreen, R. C. & Wagner, C. E.
Object Type: Report
System: The UNT Digital Library
Conceptual design considerations and neutronics of lithium fall laser fusion target chambers (open access)

Conceptual design considerations and neutronics of lithium fall laser fusion target chambers

Atomics International and Lawrence Livermore Laboratory are involved in the conceptual design of a laser fusion power plant incorporating the lithium fall target chamber. In this paper we discuss some of the more important design considerations for the target chamber and evaluate its nuclear performance. Sizing and configuration of the fall, hydraulic effects, and mechanical design considerations are addressed. The nuclear aspects examined include tritium breeding, energy deposition, and radiation damage.
Date: May 31, 1978
Creator: Meier, W. R. & Thomson, W. B.
Object Type: Article
System: The UNT Digital Library
LOFT CIS analysis: 1''-SSS-3-E inside containment penetration S-11C (open access)

LOFT CIS analysis: 1''-SSS-3-E inside containment penetration S-11C

The stress analysis performed on the 1''-SSS-3-E piping system inside containment penetration S-11C is described. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject pipe system will meet ASME Boiler and Pressure Vessel Code, Section III, Class 2 Requirements provided that additional supports (S3 and S6) are installed as recommended.
Date: October 31, 1978
Creator: Nitzel, M.E.
Object Type: Report
System: The UNT Digital Library
Stress analysis of loft (ECC) system; left side (open access)

Stress analysis of loft (ECC) system; left side

An analysis has been performed by the Applied Mechanics Branch on a new Left Side configuration of the LOFT Emergency Core Coolant (ECC) System. This system has been geometrically modified from that analyzed in a previous report, LTR 113-40. LOCE and Safe Shutdown Earthquake (SSE) were the only loading conditions considered capable of producing high stresses. Review of the analyses indicates that the new configuration passes the requirements of the ASME Code for Class 1 and 2 piping.
Date: August 31, 1978
Creator: Kido, C.
Object Type: Report
System: The UNT Digital Library
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report (open access)

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - …
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Determination of bulk diffusion lengths for angle-lapped semiconductor material via the scanning electron microscope: a theoretical analysis (open access)

Determination of bulk diffusion lengths for angle-lapped semiconductor material via the scanning electron microscope: a theoretical analysis

A standard procedure for the determintion of the minority carrier diffusion length by means of a scanning electron microscope (SEM) consists in scanning across an angle-lapped surface of a P--N junction and measuring the resultant short circuit current I/sub sc/ as a function of beam position. A detailed analysis of the I/sub sc/ originating from this configuration is presented. It is found that, for a point source excitation, the I/sub sc/ depends very simply on x, the variable distance between the surfce and the junction edge. The expression for the I/sub sc/ of a planar junction device is well known. If d, the constant distance between the plane of the surface of the semiconductor and the junction edge in the expression for the I/sub sc/ of a planar junction is merely replaced by x, the variable distance of the corresponding angle-lapped junction, an expression results which is correct to within a small fraction of a percent as long as the angle between the surfaces, 2 theta/sub 1/, is amaller than 10/sup 0/.
Date: May 31, 1978
Creator: von Roos, O.
Object Type: Report
System: The UNT Digital Library
High-temperature explosive development for geothermal well stimulation. Final report (open access)

High-temperature explosive development for geothermal well stimulation. Final report

A two-component, temperature-resistant liquid explosive called HITEX has been developed which is capable of withstanding 561/sup 0/K (550/sup 0/F) for 24 hours in a geothermal environment. The explosive is intended for the stimulation of nonproducing or marginally producing geothermal (hot dry rock, vapor-dominated or hydrothermal) reservoirs by fracturing the strata in the vicinity of a borehole. The explosive is inherently safe because it is mixed below ground downhole from two nondetonable liquid components. Development and safety tests included differential scanning calorimetry, thermal stability, minerals compatibility, drop-weight sensitivity, adiabatic compression, electrostatic discharge sensitivity, friction sensitivity, detonation arrest capability, cook-off tests, detonability at ambient and elevated pressure, detonation velocity and thin film propagation in a wedge.
Date: March 31, 1978
Creator: Schmidt, E.W.; Mars, J.E. & Wang, C.
Object Type: Report
System: The UNT Digital Library
Baseline Gas Turbine Development Program. Twenty-First Quarterly Progress Report (open access)

Baseline Gas Turbine Development Program. Twenty-First Quarterly Progress Report

Progress is reported for a program whose goals are to demonstrate an experimental upgraded gas turbine-powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine-powered, compact-size American automobile. Activity during this twenty-first program quarter has continued to emphasize development towards correcting a power deficiency in the upgraded engine. Efforts are also being directed towards reducing fuel usage through improved heat recovery and towards improving the mechanical reliability and control of the engine.
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Small power systems study technical summary report. Volume II. Inventory of small generating units in U. S. utility systems (open access)

Small power systems study technical summary report. Volume II. Inventory of small generating units in U. S. utility systems

Data identifying small (less than or equal to 10 MW) power units in the United States are tabulated. The data are listed alphabetically by state and are reported sequentially for investor owned utilities, municipal utilities, and electrical cooperatives and other utility systems. For a given utility system, the generating units are divided into steam turbines, diesel generators and gas turbines. The number and size of generating units are listed. A summary tabulation of the number of generating units of each type and total generating capacity by state is presented.
Date: May 31, 1978
Creator: Sitney, L.R.
Object Type: Report
System: The UNT Digital Library
Thin film battery/fuel cell power generating system. Final report, Task E-4, April 1976-April 1978 (open access)

Thin film battery/fuel cell power generating system. Final report, Task E-4, April 1976-April 1978

A two-year researth program to design and demonstrate the technical feasibility of a high-temperature solid-electrolyte fuel cell is described in detail. A rare-earth chromite, in particular, La /sub 95/Mg /sub 05/Cr /sub 75/Al /sub 25/0/sub 3/ was identified, synthesized by RF-sputtering tested for resistivity, thermal expansion and inertness in contact with yttria-stabilized zirconia, and was found promising as a candidate interconnection material. Films of these interconnection materials have been successfully deposited onto stabilized zirconia tubes by electrochemical vapor deposition (EVD) and the technique has been used to fabricate such films in building fuel cell stacks. Tin-doped indium oxide and antimony-doped tin oxide air electrode current collector materials have been successfully (CVD) chemically vapor deposited, as thin films, onto zirconia tubes. Fabrication procedures for the preparation of thin films of the nickel-cermet fuel electrode and yttria-stabilized zirconia solid electrolyte have been re-verified and improved for use in preparing unit cells and cell stacks on the program. An in-house extrusion technology for porous calcia-stabilized zirconia tubes has been developed and has been used to provide suitable support tubes for component combination samples, unit cell and cell stack sample preparation. Test concepts for component combinations and for unit cells and cell stacks have …
Date: March 31, 1978
Creator: Feduska, W.
Object Type: Report
System: The UNT Digital Library
Data accumulation on the methane potential of the coal beds of Colorado. Final report (open access)

Data accumulation on the methane potential of the coal beds of Colorado. Final report

A two-year project was conducted to gather data that would assist in the evaluation of the methane potential of the coal beds of Colorado. It was found that a number of closed underground coal mines in the State had reported gassy conditions or had experienced fires and explosions of varied intensity and frequency. The majority of such occurrences have been in those areas characterized by coals of relatively low (i.e., below 31%) volatile matter (VM) content. The south half of the Raton Mesa coal region (Las Animas County) and the southeastern part of the Unita region (in Gunnison and Pitkin Counties) contain coals with the lowest percentages of VM, the gassiest producing mines, and the highest grade coking coal in the State. Five active mines in Pitkin County presently are emitting a total of over 8 million cu ft of methane per day. These mines produce the highest quality metallurgical-grade coal in the western US (high-volatile A and medium-volatile bituminous). The gassy coals in these two regions range from Late Cretaceous to Paleocene in age and usually occur in areas related to igneous activity of late Tertiary age. The VM percentages of Colorado coals can be used, with some caution, …
Date: March 31, 1978
Creator: Fender, H. B. & Murray, D. K.
Object Type: Report
System: The UNT Digital Library
LOFT primary coolant addition and Control Piping System stress analysis (open access)

LOFT primary coolant addition and Control Piping System stress analysis

A stress analysis was performed on the Primary Coolant Addition and Control Piping System to determine if it met the conditions of the ASME Code, Section III, for Class 2 components. Results indicate that the Addition and Control System does not meet Section III criteria as the system is now installed. Only hanger (support) modifications are required to bring the stresses within the limits set forth in the Code. A design temperature of 459/sup 0/F was assumed for the analysis. The specified design temperature of 650/sup 0/F has been revised by ECRA's L-5713 and L-5714.
Date: October 31, 1978
Creator: Murdock, S.M.
Object Type: Report
System: The UNT Digital Library
Annual technical progress report: reactor safety, Government fiscal year 1978 (open access)

Annual technical progress report: reactor safety, Government fiscal year 1978

Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis.
Date: December 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report (open access)

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited (BNFL).
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report (open access)

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein.
Date: January 31, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library