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Clean Cities alternative fuel information series
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Geothermal R and D Project report for October 1, 1975--December 30, 1975
The Idaho National Engineering Laboratory (INEL) Geothermal Research and Development Project is conducting two major geothermal development efforts: 1) a project aimed at medium temperature (approximately 300/sup 0/F) utilization to produce electricity with supplemental direct thermal use of the energy; and 2) a low temperature (approximately 170/sup 0/F) space heating project. The first effort has progressed in the field to the successful drilling of two deep geothermal wells providing flows of the desired temperature in the Raft River Valley of south central Idaho. The second program involves the heating of government buildings and a university campus at Boise, Idaho. This report covers the period October 1, to December 30, 1975.
Date:
April 1, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1975
The data obtained from the environmental monitoring program of the Lawrence Berkeley Laboratory for the calendar year 1975 are described and general trends are discussed. (auth)
Date:
April 1, 1976
Creator:
Thomas, R. H. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Uranium in alkaline rocks
Geologic and geochemical criteria were developed for the occurrence of economic uranium deposits in alkaline igneous rocks. A literature search, a limited chemical analytical program, and visits to three prominent alkaline-rock localities (Ilimaussaq, Greenland; Pocos de Caldas, Brazil; and Powderhorn, Colorado) were made to establish criteria to determine if a site had some uranium resource potential. From the literature, four alkaline-intrusive occurrences of differing character were identified as type-localities for uranium mineralization, and the important aspects of these localities were described. These characteristics were used to categorize and evaluate U.S. occurrences. The literature search disclosed 69 U.S. sites, encompassing nepheline syenite, alkaline granite, and carbonatite. It was possible to compare two-thirds of these sites to the type localities. A ranking system identified ten of the sites as most likely to have uranium resource potential.
Date:
April 1, 1978
Creator:
Murphy, M.; Wollenberg, H.; Strisower, B.; Bowman, H.; Flexser, S. & Carmichael, I.
Object Type:
Report
System:
The UNT Digital Library
South Fork Clearwater River Habitat Enhancement, Nez Perce National Forest.
In 1984, the Nez Perce National forest and the Bonneville Power Administration entered into a contractual agreement which provided for improvement of spring chinook salmon and summer steelhead trout habitat in south Fork Clearwater River tributaries. Project work was completed in seven main locations: Crooked River, Red River, Meadow Creek Haysfork Gloryhole, Cal-Idaho Gloryhole, Fisher Placer and Leggett Placer. This report describes restoration activities at each of these sites.
Date:
April 1, 1992
Creator:
Siddall, Phoebe
Object Type:
Report
System:
The UNT Digital Library
Technicon autoanalyzers: functional description
This document describes and specifies a computer automation system for the Technicon AutoAnalyzers (I, II, and CSM-6 colorimeter). Operator inputs and interaction during the analysis run are described. Computer outputs during and at the end of the run are described and illustrated. The computer calculates concentrations, monitors quality control, and prepares reports.
Date:
April 1, 1976
Creator:
Crawford, Richard W. & Barton, George W., Jr.
Object Type:
Report
System:
The UNT Digital Library
Some effects of magnetic walls on the transverse motion of an intense beam of charged particles
The focusing properties of a magnetic medium surrounding a beam of relativistic particles were examined. The magnitude of the magnetic forces generated by the wall is proportional to the beam current. For a current of the order of 10 kA, significant magnetic field gradients are obtained. It was concluded that the series of structures studied is not satisfactory for providing focusing of an intense beam of particles. However, the characteristics of the transverse forces suggest a method of constructing a passive, current-dependent, deflector for an intense beam.
Date:
April 1, 1976
Creator:
Neil, V. K.
Object Type:
Report
System:
The UNT Digital Library
Integration of Transients in Axisymmetrical Cavities for Accelerators: Formulation and applications to BNL Photocathode Gun
This note provides a sketch of the formalism used for the Integration of Transients in Axisymmetrical Cavities for Accelerators, (ITACA). Application to study the BNL Photocathode Gun via the code ITACA is also included.
Date:
April 1, 1992
Creator:
Parsa, Z. (Brookhaven National Lab., Upton, NY (United States)) & Serafini, L. (Istituto Nazionale di Fisica Nucleare, Milan (Italy) Milan Univ. (Italy))
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory quarterly report to ERDA Nuclear Research and Applications Division, January--March 1976. [Use of /sup 90/SrF/sub 2/ and /sup 137/CsCl WESF capsules as heat sources]
Progress in the strontium heat source and beneficial isotopes utilization programs is discussed. The couples required for the long-term tests compatibility were fabricated and the tests are under way. The 1000-hr tests were completed, and examination of the test couples has been started. Compatibility testing of two full-scale WESF /sup 90/SrF/sub 2/ capsules at 800/sup 0/C has started. Additional short-term compatibility testing of 25 potential containment materials are also under way. The 5000-hr aging tests of Hastelloy C-4 were completed and the specimens are being examined. Conceptual flowsheets were drawn up for recovery of various combinations of radioisotopes from stored high level wastes, and rough cost estimates were made. Additional calculations of /sup 137/CsCl capsule irradiation efficiency are reported. Conclusions of a study of the beneficial utilization of WESF /sup 90/SrF/sub 2/ capsules are presented.
Date:
April 1, 1976
Creator:
Fullam, H. T. & Harmon, K. M.
Object Type:
Report
System:
The UNT Digital Library
CALOR: a Monte Carlo program package for the design and analysis of calorimeter systems. [In FORTRAN IV]
CALOR is a Monte Carlo program package, written in FORTRAN IV, that is designed to assist experimentalists in evaluating and analyzing different types of calorimeter systems that are used in many high-energy physics experiments to determine the energy and direction of incident hadrons, leptons, and photons. This code package is intended to be used with the code package HETC, which supplies needed information on the transport of hadrons and on the spatial location of the electromagnetic source energy. Input and output for a sample problem are presented. 3 figures, 1 table.
Date:
April 1, 1977
Creator:
Gabriel, T. A.; Amburgey, J. D. & Bishop, B. L.
Object Type:
Report
System:
The UNT Digital Library
Effects of substrate temperature on silicon nitride cracking of beam lead devices during thermocompression wobble bonding
Recent failures in several completed Sandia Laboratories' electronic systems have traced to specific format 25 beam lead transistors and diodes. More extensive failure analysis on the devices showed them to exceed their respective specifications in electrical leakage. All of the failed devices were observed to have one thing in common: cracked silicon nitride over the beams. These observations triggered several investigations to determine if cracked silicon nitride causes electrical failures, where (processing, assembly, etc.) nitride cracking occurs, and when nitride cracking can be reduced or eliminated. The effects of changes in substrate temperature and force upon nitride cracking during bonding are described. Devices were bonded at 150, 200, and 250/sup 0/C, and at 250 and 525 gms of force, and the amount of nitride damage in the bonding operation was determined. Neither parameter had large effects in cracking. The pulled strength and failure modes were recorded. The results showed that approximately 22 percent of the devices developed silicon nitride cracks over the beams. Total production handling and processing result in 80 to 90 percent of the devices having cracked nitride. Although the sample size is small (63 devices), it does not appear that the cracking is dependent on the substrate …
Date:
April 1, 1976
Creator:
Bushmire, D. W.; Chavez, E. L. & Finley, M. H.
Object Type:
Report
System:
The UNT Digital Library
Alloy steel bars and shapes (ASME SA-479 with additional requirements)
None
Date:
April 1, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Maintenance approaches and practices in selected foreign nuclear power programs and other US industries: Review and lessons learned
The Commission published a Notice of Proposed Rule-making on Maintenance of Nuclear Power Plants on November 28, 1988, spelling out NRC's expectations in maintenance. In preparing the proposed rule, the NRC reviewed maintenance practices in other countries and considered maintenance approaches in other industries in this country. As a result of the review of maintenance practices, it was concluded that certain practices in the following areas have been found to contribute significantly to effective maintenance: (1) systems approach; (2) effectiveness monitoring; (3) technician qualifications and motivation; and (4) maintenance organization. 87 refs., 26 figs., 2 tabs.
Date:
April 1, 1990
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
How to estimate the solubility of an insoluble compound: 1,3,5-triamino-2,4,6-trinitrobenzene (TATB)
A simple method for estimating the solubility of TATB in various solvents is presented. We consider it unlikely that a solvent will be found in which TATB is more soluble than 0.1 percent (w/v). Exceptions are the so-called superacids in which the solubility of TATB exceeds 20 percent (w/v).
Date:
April 1, 1977
Creator:
Selig, W.
Object Type:
Article
System:
The UNT Digital Library
Experiment prediction for Loft Nonnuclear Experiment L1-4. [PWR]
None
Date:
April 1, 1977
Creator:
White, J. R.; Berta, V. T. & Holmstrom, H. L. O.
Object Type:
Report
System:
The UNT Digital Library
Status of beta- and gamma-decay and spontaneous-fission data from transactinium isotopes
Several categories of ..beta..- and ..gamma..-related decay data for the transactinium isotopes are assessed in the light of their potential use in applied areas. The status as of August, 1975, of these data is summarized for 142 transactinium nuclides with 228 less than or equal to A less than or equal to 257 by the listing of experimental values and errors where known. Several useful compilations of transactinium-isotope decay data are discussed. Recent developments related to the yields and energy distributions of prompt and delayed neutrons from spontaneous fission are briefly treated. Comments and observations about the interrelation of the important nuclear-data activities of measurement, compilation and evaluation and needs assessment are given. The applications-oriented file of decay data prepared at our laboratory for ENDF/B is discussed. Finally, a summary by G. Rudstam of the status of the OSIRIS work on delayed-neutron energy spectra of individual precursors is included.
Date:
April 1, 1976
Creator:
Reich, C. W.
Object Type:
Report
System:
The UNT Digital Library
Final report on investigation of stability of organic materials in salt cake
On the basis of this work the following conclusions, which all contribute to confidence that salt cake is stable against exothermic reactions, were reached. Organics added to the waste tanks were not nitrated at the time of addition and cannot have been subsequently transformed to detonatable nitrated organics. Whatever organic has found its way into the tanks has been and will be essentially unaffected by radiation. Mixtures of the types of organics which could have been added to the waste tanks with either simulated salt cake or pure sodium nitrate are not detonatable. The maximum amount of organic which could have been added to the waste tanks is less than 0.9 weight percent of the salt cake, a concentration far below the concentration required to support combustion. The many years during which the liquid high-level waste was boiling, and the subsequent evaporation-crystallization processing, have allowed many of the more volatile organics to be distilled off, further reducing the maximum expected concentration of organics. The occurrence of an explosive exothermic reaction of an organic in the waste tanks would require concentration and mixing by an unknown and uncontrolled means. The mixture would then have to remain in its concentrated state long …
Date:
April 1, 1976
Creator:
Beitel, G. A.
Object Type:
Report
System:
The UNT Digital Library
Research and Engineering Division semiannual report, KK process development and technology, May 1, 1975--October 31, 1975
This document represents the second of a series reporting on a semiannual basis the activities supported by KK funds in the areas of process development. These research and engineering activities have the goal of improving the performance of the plutonium processing and waste management programs being operated by the Atlantic Richfield Hanford Company.
Date:
April 1, 1976
Creator:
Fox, R. D. & Manry, C. W. (eds.)
Object Type:
Report
System:
The UNT Digital Library
Cold regions isotope applications
Pacific Northwest Laboratories (PNL) started the Cold Regions Isotope Applications Program in FY-1975 to identify special conditions in the Arctic and similar geographic areas (Cold Regions) where radioisotope power, heater, or sterilization systems would be desirable and economically viable. Significant progress was made in the first year of this program and all objectives for this initial 12-month period were achieved. The major conclusions and recommendations resulting for this effort are described below. The areas of interest covered include: radiosterilization of sewage; heating of septic tanks; and radioisotope thermoelectric generators as power sources for meteorological instruments and navigational aids. (TFD)
Date:
April 1, 1976
Creator:
Perrigo, L. D. & Divine, T. E.
Object Type:
Report
System:
The UNT Digital Library
TRUEX hot demonstration
In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.
Date:
April 1, 1990
Creator:
Chamberlain, D. B.; Leonard, R. A.; Hoh, J. C.; Gay, E. C.; Kalina, D. G. & Vandegrift, G. F.
Object Type:
Report
System:
The UNT Digital Library
Study of the effects of radiation of nucleic acids and related compounds. Progress report, August 15, 1975--August 14, 1976
Ionizing radiation produces genetic effects in biological systems. Since genetic effects are usually the result of modifications of DNA or sometimes of RNA, interest is being centered on the chemical and physical nature of radiation-induced lesions to nucleic acids and their components. These investigations have revealed the enormous complexity of chemical events and the possible degradation of nucleic acids by strand breakage. Therefore, work in the ionization radiation of nucleic acids has proceeded along a dual course. On the one hand, molecular changes have been characterized for a number of primary radiation products. On the other hand, strand breakage has been investigated intensively as a direct primary event. Both of these aspects were emphasized in our research last year. We succeeded in improving the synthesis of 5-hydroxy-methyl thymine (..cap alpha..-TOOH). ..cap alpha..-TOOH was found to be much more effective than cis-5,6-dihydro-6-hydroperoxy-5-hydroxy thymine (6-TOOH) in the inactivation of transforming DNA of H. influenzae cells although ..cap alpha..-TOOH is much less reactive chemically than 6-TOOH. 6-TOOH causes inactivation and acts as an inhibitor of DNA synthesis in mammalian cells. In addition, evidence may indicate that 6-TOOH does not induce strand breaks directly in DNA although we showed that 6-TOOH is a clastogenic …
Date:
April 1, 1976
Creator:
Wang, S. Y.
Object Type:
Report
System:
The UNT Digital Library
Simple method to unfold NE 213 and stilbene neutron spectral data
A very simple method is proposed wherein recoil proton scintillation data are reduced using the derivative unfolding technique. The approximations described require minimal calculation or storage and may be readily implemented on a mini computer. A digital filter is incorporated which yields a smoothed approximation to the slope of the pulse-height distribution, with error estimates. In order to accurately represent the scintillator light output without introducing discontinuities in the unfolded spectrum, the light output data are fitted using B-splines whose first and second derivatives are continuous.
Date:
April 1, 1976
Creator:
Slaughter, D. R.
Object Type:
Article
System:
The UNT Digital Library
Physical protection of nuclear facilities quarterly progress report, October--December 1976
Activities included the preparation of presentations for the NRC review committee. Also, a draft program plan on the Protection of Nuclear Materials for both fixed facilities and in-transit systems was submitted to the NRC. Other activities have focused primarily on the development of evaluation methodologies. These efforts have included the development of a computer graphics implementation of EASI (Estimate of Adversary Sequence Interruption), engagement model developments, ISEM (Insider Safeguards Effectiveness Model) documentation, pathing algorithm improvements, and facility characterization methodology improvements. A large effort has been expended in defining and interfacing with possible contractual support involvements. Areas of these involvements include a generic safeguards data base, fault tree analysis techniques, physical protection modeling, human attribute definitions, neutralization modeling, and safeguards network symbology models.
Date:
April 1, 1977
Creator:
Chapman, L. D. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Effects of fueling profiles on plasma transport
A one-dimensional (1-D), multifluid transport model is used to investigate the effects of particle fueling profiles on plasma transport in an ignition-sized tokamak (TNS). Normal diffusive properties of plasmas will likely maintain the density at the center of the discharge even if no active fueling is provided there. This significantly relaxes the requirements for fuel penetration. Not only is lower fuel penetration easier to achieve, but it may have the advantage of reducing or eliminating density gradient-driven trapped particle microinstabilities. Simulation of discrete pellet fueling indicates that relatively low velocity (approximately 10/sup 3/ m/sec) pellets may be sufficient to fuel a TNS-sized device (approximately 1.25-m minor radius), to produce a relatively broad, cool edge region of plasma which should reduce the potential for sputtering, and also to reduce the likelihood of trapped particle mode dominated transport. Low penetrating pellets containing up to 10 to 20 percent of the total plasma ions can produce fluctuations in density and temperature at the plasma edge, but the pressure profile and fusion alpha production remain almost constant.
Date:
April 1, 1978
Creator:
Mense, A. T.; Houlberg, W. A.; Attenberger, S. E. & Milora, S. L.
Object Type:
Report
System:
The UNT Digital Library
NACHOS: a finite element computer program for incompressible flow problems. Part I. Theoretical background
The theoretical background for the finite element computer program, NACHOS, is presented in detail. The NACHOS code is designed for the two-dimensional analysis of viscous incompressible fluid flows, including the effects of heat transfer. A general description of the fluid/thermal boundary value problems treated by the program is described. The finite element method and the associated numerical methods used in the NACHOS code are also presented. Instructions for use of the program are documented in SAND77-1334.
Date:
April 1, 1978
Creator:
Gartling, D. K.
Object Type:
Report
System:
The UNT Digital Library