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National uranium resource evaluation program: hydrogeochemical and stream sediment reconnaissance basic data for Ely quadrangle, Nevada; Utah (open access)

National uranium resource evaluation program: hydrogeochemical and stream sediment reconnaissance basic data for Ely quadrangle, Nevada; Utah

Field and laboratory data are presented for 1937 sediment samples from the Ely Quadrangle, Nevada; Utah. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.
Date: October 15, 1981
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Transport properties of multi-component fluids and of suspensions (open access)

Transport properties of multi-component fluids and of suspensions

This report describes work performed under grant No. DE-FG03-88ER13911 for the period June 15, 1988 through June 14, 1989. During this time, significant progress was made in the derivation of the fundamental equations describing suspensions and multicomponent fluid flow. We first considered a system consisting of spherical heavy (Brownian) particles immersed in a bath of spherical particles. The deviations of the bath from equilibrium are due to the nonequilibrium motions of the Brownian particles. The densities of the bath and of a Brownian particle are similar. An expansion in powers of the mass ratio, yields a Fokker-Planck equation for the distribution function of the Brownian particles, including the effects of direct and hydrodynamic interactions amongst these particles. The effect of the Brownian particle motion on the bath properties has been described. The conditions under which a closed equation for the coordinate space distribution function, can be obtained have been investigated and a Smoluchowski equation for this quantity has been derived.
Date: September 15, 1989
Creator: Oppenheim, I. & McBride, J.
Object Type: Report
System: The UNT Digital Library
BNL neutral beam development group. Progress report, FY 1979 (open access)

BNL neutral beam development group. Progress report, FY 1979

The objective of the BNL Neutral Beam Program is to develop a 250 keV neutral beam system suitable for heating experiments in toroidal or mirror plasma devices. The system will be based on acceleration and neutralization of negative hydrogen ions produced in and directly extracted from a source. The objective of source studies is to develop a unit delivering 10 A of negative ion currents in pulses of 1 s duration or longer, operating with extracted current densities of at least 0.5 A/cm/sup 2/ and having acceptable power and gas efficiencies and good beam optics. The 250 keV accelerator development work covers different structures, including those separated from the source by a bending magnet or a beam transfer system. During FY 1979 substantial progress was achieved toward the objectives of the program; in the same period the BNL program was reviewed by a panel, resulting in suggestions for a better orientation toward prospective users' requirements and in establishment of contacts with Princeton Plasma Physics Laboratory (TFTR Project) and Lawrence Berkeley and Livermore Laboratories (MFTF Project). A cooperative effort with Westinghouse was initiated in the second half of FY 1979 in order to utilize industrial facilities and expertise.
Date: January 15, 1980
Creator: Prelec, K. & Sluyters, T.
Object Type: Report
System: The UNT Digital Library
Spert I Destructive Test Program Safety Analysis Report (open access)

Spert I Destructive Test Program Safety Analysis Report

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 …
Date: June 15, 1962
Creator: Spano, A. H. & Miller, R. W.
Object Type: Report
System: The UNT Digital Library
Secondary Isotope Effects in Molecular Structure (open access)

Secondary Isotope Effects in Molecular Structure

A study was made to determine whether secondary iso tope effects also occur in molecular structure. Electron diffraction studies were carried out on ethane and deuteroethane. In C/sub 2/H/sub 6/ the mean C-C and C-H bond lengths found agreed very closely with values determined for other paraffin hydrocarbons, and the C--H bond showed a normal primary isotope effect (~ 0.005 A) similar to that found in methane when H is replaced by O. The output of the leastsquares analysis suggested that the mean C-- C bond length in C/sub 2/D/sub 6/ is shorter than in C/sub 2/H/sub 6/ and by about 0.004 A. Th e decrease seemed to be real for the apparent uncertainty was not much greater than 0.001 A. (M.C.G.)
Date: June 15, 1962
Creator: Bartell, L. S.
Object Type: Article
System: The UNT Digital Library
LIMB Demonstration Project Extension (open access)

LIMB Demonstration Project Extension

The basic goal of the Limestone Injection Multistage Burner (LIMB) demonstration is to extend LIMB technology development to a full- scale application on a representative wall-fired utility boiler. The successful retrofit of LIMB to an existing boiler is expected to demonstrate that (a) reductions of 50 percent or greater in SO{sub x} and NO{sub x} emissions can be achieved at a fraction of the cost of add-on FGD systems, (b) boiler reliability, operability, and steam production can be maintained at levels existing prior to LIMB retrofit, and (c) technical difficulties attributable to LIMB operation, such as additional slagging and fouling, changes in ash disposal requirements, and an increased particulate load, can be resolved in a cost-effective manner. The primary fuel to be used will be an Ohio bituminous coal having a nominal sulfur content of 3 percent or greater.
Date: December 15, 1988
Creator: unknown
Object Type: Report
System: The UNT Digital Library
LIMB Demonstration Project Extension (open access)

LIMB Demonstration Project Extension

The basic goal of the Limestone Injection Multistage Burner (LIMB) demonstration is to extend LIMB technology development to a full- scale application on a representative wall-fired utility boiler. The successful retrofit of LIMB to an existing boiler is expected to demonstrate that (a) reductions of 50 percent or greater in SO{sub x} and NO{sub x} emissions can be achieved at a fraction of the cost of add-on FGD systems, (b) boiler reliability, operability, and steam production can be maintained at levels existing prior to LIMB retrofit, and (c) technical difficulties attributable to LIMB operation, such as additional slagging and fouling, changes in ash disposal requirements, and an increased particulate load, can be resolved in a cost-effective manner. The primary fuel to be used will be an Ohio bituminous coal having a nominal sulfur content of 3 percent or greater.
Date: June 15, 1989
Creator: unknown
Object Type: Report
System: The UNT Digital Library
DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C (open access)

DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C

The mechanisms and kinetics of the loss of boron during heating at 1135 deg C under various dynamic environments were determined from powder compacts of 5 wt% elemental boron dispersed in matrices of Fe, Cr, Ni, Si, Fe/sub 2/O/sub 3/, Cr/sub 2/O/sub 3/, NiO, and SiO/sub 2/, compacts of austenitic stainless steel alloy powder containing 0.25 wt% boron, and wrought specimens of 0.13 wt% boron-- stainless steel alloy. The compacts containing 5 wt% boron were heat treated in vacuum, highpurity argon, wet helium, and hydrogen. With the exception of those heat treated in hydrogen, significant boron losses occurred only when a supply of oxygen, either from the sample itself or as a deliberate addition to the heat- treating environment, was available. Correspondingly, the loss mechanism is postulated to be the oxidation of boron to boron sesquioxide and its volatilization from the sample. The loss rate is controlled by the volatilization rate of the oxide which is directly influenced by structure of the compact and sintering environment. Independent of the chemical nature of the matrix, boron losses were incurred during heat treatment in hydrogen. Variations of the water content of the hydrogen from 7 to 460 ppm did not significantly influence …
Date: September 15, 1961
Creator: Cherubini, J.H.
Object Type: Report
System: The UNT Digital Library
Summary report on the Solar Consumer Assurance Network (SOLCAN) Program Planning Task in the southern region (open access)

Summary report on the Solar Consumer Assurance Network (SOLCAN) Program Planning Task in the southern region

The goal of the SOLCAN Program Planning Task is to assist in the development, at the state and local levels, of consumer assurance approaches that will support the accelerated adoption and effective use of new products promoted by government incentives to consumers to meet our nation's energy needs. The task includes state-conducted evaluations and state SOLCAN meetings to identify consumer assurance mechanisms, assess their effectiveness, and identify and describe alternative means for strengthening consumer and industry assurance in each state. Results of the SOLCAN process are presented, including: a Solar Consumer Protection State Assessment Guide; State Solar Consumer Assurance Resources for Selected States; State Solar Consumer Protection Assessment Interviews for Florida; and state SOLCAN meeting summaries and participants. (LEW)
Date: March 15, 1981
Creator: Browne, M. B.
Object Type: Report
System: The UNT Digital Library
Price allocation guidelines January 1980: Low-cost solar array project (open access)

Price allocation guidelines January 1980: Low-cost solar array project

The price allocation guidelines (PAG) are an integrated set of specific cost targets for several task areas within the Low-cost Solar Array (LSA) Project. PAG is a working tool of LSA Project management designed to provide consistent and meaningful guidelines for costs of polycrystalline silicon material, sheet, cells, encapsulants, and module manufacturing. It is expected that advanced photovoltaic concepts derived from industry and the research community can be developed so that it will be possible by the end of 1982 to demonstrate production processes, all process steps, and prototype equipment required to manufacture flat-plate photovoltaic modules. This demonstration would incorporate production rates and product quality consistent with a specific market price determined by the program. This stage of development has been referred to as Technical Readiness. A goal of $0.70 per peak watt (1980 dollars) has been established for the cost of electricity generated by photovoltaic modules. The processes for producing modules demonstrated to be technically ready must be amenable to scale-up so that this price goal can eventually be achieved in the marketplace. The guidelines described in this document allocate portions of that goal to each module component. Sheet materials derived from the following five technologies are considered: Czochralski, …
Date: January 15, 1980
Creator: Aster, R. W.
Object Type: Report
System: The UNT Digital Library
Multiple-reflection optical gas cell. [DOE Patent Application] (open access)

Multiple-reflection optical gas cell. [DOE Patent Application]

A multiple-reflection optical cell for Raman or fluorescence gas analysis consists of two spherical mirrors positioned transverse to a multiple-pass laser cell in a confronting plane-parallel alignment. The two mirrors are of equal diameter but possess different radii of curvature. The spacing between the mirrors is uniform and less than half of the radius of curvature of either mirror. The mirror of greater curvature possesses a small circular portal in its center which is the effective point source for conventional Fl double lens collection optics of a monochromator-detection system. Gas to be analyzed is flowed into the cell and irradiated by a multiply-reflected composite laser beam centered between the mirrors of the cell. Raman or fluorescence radiation originating from a large volume within the cell is: (1) collected via multiple reflections with the cell mirrors; (2) partially collimated; and (3) directed through the cell portal in a geometric array compatible with Fl collection optics.
Date: June 15, 1981
Creator: Matthews, T.G.
Object Type: Patent
System: The UNT Digital Library
Water testing of the inducer pump. [LMFBR] (open access)

Water testing of the inducer pump. [LMFBR]

The inducer pump, designed and fabricated as a test article to evaluate the inducer/impeller pump concept for providing improved suction performance of large sodium pumps, met or exceeded all performance goals. The inducer stage in front of the centrifugal impeller dramatically reduces the size of pumps. It was demonstrated that the inducer can operate at suction specific speeds in excess of 35,000, whereas conventional centrifugal pumps have demonstrated capability to only 12,000. The inducer pump employs several components of the 2000 and 4000 gpm NaK pumps from the Connecticut Aircraft Nuclear Engine Laboratory (CANEL) Programs. Use of the volute, thermal barrier and shaft oil seal from the CANEL pumps allowed acceleration and cost reduction of the Inducer Pump Program.
Date: September 15, 1977
Creator: Dunn, C. & Hoshide, R.K.
Object Type: Report
System: The UNT Digital Library
Technical study for the chemical cleaning of Dresden-1. Volume I, Section 1 and 2 (open access)

Technical study for the chemical cleaning of Dresden-1. Volume I, Section 1 and 2

A feasibility study has been completed to decontaminate the primary system of the Dresden-1 Nuclear Power Unit operated by Commonwealth Edison Company of Illinois. Available data initially were searched to determine the state of the art. Solvents based on organic acids and chelates gave unsatisfactory deontamination factors or unacceptable corrosion rates when evaluated for cleaning of specimens from the Dresden-1 primary system, under static and dynamic conditions. A new proprietary cleaning solution, Dow Solvent NS-1, was successfully applied in these laboratory studies.
Date: June 15, 1977
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Equation of state of beryllium (open access)

Equation of state of beryllium

A new, wide-range equation of state (EOS) has been constructed for Be. The composite theoretical model incorporates ionization equilibrium and condensed-matter and multiphase physics. It also satisfies all thermodynamic equilibrium constraints. The theoretical EOS has been compared with all available high-pressure and high-temperature Be data, and satisfactory agreement is generally achieved. The most interesting feature is the theoretical prediction of melting at just below 220 GPa (2 Mb), indicating an extremely wide pressure range for solid Be. A striking feature is the appearance of shell-structure effects in physical-process paths: 2 large loops appear on the principal Hugoniot and the behavior of release isentropes from rho = rho/sub 0/ is significantly affected.
Date: September 15, 1977
Creator: Graboske, H. & Wong, L.
Object Type: Report
System: The UNT Digital Library
Generating technology assessment. Phase I work plan, Task 1 report (open access)

Generating technology assessment. Phase I work plan, Task 1 report

A plan of work outlining information to assess electric generating technologies is presented. Projections are made of realistic and understandable engineering and cost assessments of nonnuclear electrical generating technologies. A computer-based method of producing such engineering and cost estimates for use by EIA's Coal and Electric Power Analysis Division is to be developed and implemented. Technologies and processes to be assessed are: all nonnuclear conventional and nonconventional (coal gasification, advanced combustion turbines, atmospheric fluidized bed combustion, fuel cells, geothermal, solar thermal and photovoltaics, biomass conversion to electricity, ocean thermal, wind, and MHD). Engineering specifications recommended for determination are listed. Compatibility of the technologies are to be assessed with EIA models: MEFS, LEAP, and NCM.
Date: October 15, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Development of tailored ceramics for geologic storage of nuclear wastes. Quarterly progress report, January 1-March 31, 1980 (open access)

Development of tailored ceramics for geologic storage of nuclear wastes. Quarterly progress report, January 1-March 31, 1980

In the second quarter of activities on developing Tailored Ceramic waste forms for SRP waste compositions, emphasis was on the chemistry controlling the incorporation of the waste elements into the crystalline phases of the high-alumina content ceramic and the major factors affecting the consolidation process. Research on the design and synthesis of oxide and phosphate ceramic waste forms has continued with emphasis on fluorite-structure oxides and on rare earth phosphates with the monazite structure. Dissolution studies to date indicate that monazite is very stable.
Date: May 15, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Intermediate-Size Inducer Pump design report. [LMFBR] (open access)

Intermediate-Size Inducer Pump design report. [LMFBR]

This report summarizes the mechanical, structural, and hydrodynamic design of the Intermediate-Size Inducer Pump (ISIP). The design was performed under Atomics International's DOE Base Technology Program by the Atomics International and Rocketdyne Divisions of Rockwell International. The pump was designed to utilize the FFTF prototype pump frame as a test vehicle to test the inducer, impeller, and diffuser plus necessary adapter hardware under simulated Large Scale Liquid Metal Fast Breeder Reactor service conditions. The report describes the design requirements including the purpose and objectives, and discusses those design efforts and considerations made to meet the requirements. Included in the report are appendices showing calculative methods and results. Also included are overall assembly and layout drawings plus some details used as illustrations for discussion of the design results and the results of water tests performed on a model of the inducer.
Date: June 15, 1979
Creator: Boardman, T.J.
Object Type: Report
System: The UNT Digital Library
Review of hydrogen isotope permeability through materials (open access)

Review of hydrogen isotope permeability through materials

This report is the first part of a comprehensive summary of the literature on hydrogen isotope permeability through materials that do not readily form hydrides. While we mainly focus on pure metals with low permeabilities because of their importance to tritium containment, we also give data on higher-permeability materials such as iron, nickel, steels, and glasses.
Date: August 15, 1983
Creator: Steward, S.A.
Object Type: Report
System: The UNT Digital Library
Technical study for the chemical cleaning of Dresden-1 DNS-D1-016. Volume VII. Appendices IX thru XIV (open access)

Technical study for the chemical cleaning of Dresden-1 DNS-D1-016. Volume VII. Appendices IX thru XIV

Appendices are presented which contain information concerning the decontamination of Dresden-1; consultant's opinions; proceedings of the American Power Conference, Volume 37, 1975; health physics reports; toxicological properties and industrial handling hazards of Dow solvent NS-1; and expected radiation dose rates in the new Dresden station radioactive waste processing building.
Date: June 15, 1977
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Safety Calculations for MsSRE (open access)

Safety Calculations for MsSRE

A number of conceivable reactivity accidents were analyzed, using conservatively pessimistic assumptions and approximations, to permit evaluation of reactor safety. Most of the calculations, which are described in detail, were performed by a digital kinetics program, MURGATROYD. Some analog analyses were also made. None of the accidents which were analyzed lead to catastrophic failure of the reactor, which is the primary consideration. Some internal damage to the reactor from undesirably high temperatures could result from extreme cold- slug accidents, premature criticality during filling, or uncontrolled rod withdrawal. Each of these accidents could happen only by compounded failure of protective devices, and in each case there exists means of effective corrective action independent of the primary protection, so that damage is unlikeIy. The calculated response to arbitrary ramp and step additions of reactivity show that damaging pressures could occur only if the addition is the equivalent of a step of about 1% delta k/k or greater. (auth)
Date: May 15, 1962
Creator: Haubenreich, P.N. & Engel, J.R.
Object Type: Report
System: The UNT Digital Library
Analysis of Vanadium in Milk Powder by Neutron Activation Analysis Using a Rapid Radiochemical Separation of 3.77-Minute Vanadium-52 (open access)

Analysis of Vanadium in Milk Powder by Neutron Activation Analysis Using a Rapid Radiochemical Separation of 3.77-Minute Vanadium-52

A procedure is described for the activation determination of V in powdered milk using 3.77-min V/sup 52/. The quantity of V in the sample is obtained by comparing the V/sup 52/ radioactivity found in the test sample with the V/sup 52/ radioactivity in a V comparator sample that is treated in the same manner as the test sample. The procedure can also be used for the determination of V in a variety of materials. (P.C.H.)
Date: November 15, 1963
Creator: Molinski, V. J.; Wahl, W. H. & Strain, W. H.
Object Type: Article
System: The UNT Digital Library
Discharge circuits and loads (open access)

Discharge circuits and loads

This will be an overview in which some of the general properties of loads are examined: their interface with the energy storage and switching devices; general problems encountered with different types of loads; how load behavior and fault modes can impact on the design of a power conditioning system (PCS).
Date: October 15, 1980
Creator: Sarjeant, W. J.
Object Type: Report
System: The UNT Digital Library
Utilization of coal associated minerals. Quarterly report No. 10, January 1-March 31, 1980 (open access)

Utilization of coal associated minerals. Quarterly report No. 10, January 1-March 31, 1980

In the preceding quarterly report, it was reported that while sampling the Solvent Refined Coal II (SRC II) pilot plant at Fort Lewis, Washington, the plant went down and vacuum bottoms waste material representing the minerals flow at the last steady state condition were obtained. This plant has been sampled again and samples of the incoming feed coal, sized coal and vacuum bottoms waste material were obtained. As part of our effort to trace the same mineral suite through mining, preparation and conversion, new samples of feed coal, cleaned coal and refuse were obtained from the District 4 commercial preparation plant. This preparation plant supplies coal to the SRC II pilot plant at Fort Lewis, Washington. A study of the thermal insulating properties of fired flyash based structural materials was completed and is included.
Date: July 15, 1980
Creator: Slonaker, J. F.; Buttermore, W. H.; Carlisle, J. A.; Durham, D. L.; Muter, R. B. & Alderman, J. K.
Object Type: Report
System: The UNT Digital Library
Integrated dry NO sub x /SO sub 2 emissions control system (open access)

Integrated dry NO sub x /SO sub 2 emissions control system

This project's goal is to demonstrate the removal up to 70% of the NO{sub x} and 70% of the SO{sub 2} emissions from coal fired utility boilers. It will establish an alternative emissions control technology integrating a combination of several processes, while minimizing capital expenditures and limiting waste production to dry solids that are handled with conventional ash removal equipment. These processes include low-NO{sub x} burners, NO{sub x} ports and urea injection for NO{sub x} control, sodium or calcium based sorbent injection for SO{sub 2} control, and flue gas humidification to enhance the reactivity of the SO{sub 2} control compound.
Date: October 15, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library