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STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS
ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric acid solution containing 0.13M metal ions at 35 deg C. (auth)
Date:
February 12, 1962
Creator:
Anderson, D. R. & Rhodes, D. W.
System:
The UNT Digital Library
Study of impurities in the Tandem Mirror Experiment using extreme-ultraviolet spectroscopy
Impurities in the Tandem Mirror Experiment (TMX) have been studied using extreme ultraviolet spectroscopy. Three time-resolving absolutely-calibrated normal-incidence monochromators, one on each section of TMX, were used to study the impurity emissions in the wavelength range of 300 A to 1600 A. The instruments on the east end cell and central cell were each capable of obtaining spatially-resolved profiles from 22 chords of the plasma simultaneously while the instrument on the west end cell monitored the central chord. The impurities identified in TMX were carbon, nitrogen, oxygen, and titanium. Emphasis was placed upon determining the impurity densities and radiated power losses of the central cell; results indicate that the impurity concentrations were low - less than 0.4% for each species - and that less than 10% of the total net trapped neutral beam power was lost to radiation. The use of titanium gettering on the central cell walls was observed to decrease the brightnesses of singly- and doubly-ionized carbon and oxygen in the central cell plasma. In the end cells, oxygen was the main impurity with a concentration of about 1.5% and was injected by the neutral beams; the other impurities had concentrations of about 0.5%. Radiation losses from the …
Date:
May 12, 1982
Creator:
Strand, O. T.
System:
The UNT Digital Library
Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962
Progress is reported on thermonuclear research. Separate abstracts were prepared for 8 of the 10 sections. Design and engineering service reports and notes are given in the remaining sections. (M.C.G.)
Date:
September 12, 1962
Creator:
unknown
System:
The UNT Digital Library
Technical-economic assessment of the production of methanol from biomass. Executive summary. Final research report
The results are presented of a comprehensive systems study which assessed the engineering and economic feasibilities of the production of methanol from biomass utilizing existing technology. The three major components of the biomass to methanol system assessed are the availability of biomass feedstocks, the thermochemical conversion of biomass to methanol fuels, and the distribution and markets for methanol fuels. The results of this study show that methanol fuel can be produced from biomass using commercially available technology in the near term, and could be produced economically in significant quantities in the mid-to-late 1980's when advanced technology is available.
Date:
July 12, 1979
Creator:
Wan, E. I.; Simmons, J. A.; Price, J. D. & Nguyen, T. D.
System:
The UNT Digital Library
Police-Community Relations: Selected References
This report provides a bibliography of resources related to police and community relations.
Date:
March 12, 1970
Creator:
Loo, Shirley
System:
The UNT Digital Library
National Welfare Standard--Problems and Proposals
This report attempts to present some of the factors which must be examined and the issues which must be decided in considering a proposal for national welfare standard, as well as a summary of the arguments which can be made for and against the adoption of national standard.
Date:
February 12, 1969
Creator:
Fullerton, William D.
System:
The UNT Digital Library
The Seniority System in Congress: A Selected Bibliography
This report provides a bibliography of resources related to the seniority system in Congress.
Date:
November 12, 1969
Creator:
Kravitiz, Walter
System:
The UNT Digital Library
The Peace Symbol
This report explains "peace symbols" through an example of British pacifist groups campaigning for nuclear disarmament. The report also describes how symbols are interpreted and used by different groups of people.
Date:
February 12, 1970
Creator:
Goral, Marguerite
System:
The UNT Digital Library
Propane Vibrational Analysis
Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
Date:
June 12, 1962
Creator:
Marshall, G. D.
System:
The UNT Digital Library
System model for analysis of the mirror fusion-fission reactor
This report describes a system model for the mirror fusion-fission reactor. In this model we include a reactor description as well as analyses of capital cost and blanket fuel management. In addition, we provide an economic analysis evaluating the cost of producing the two hybrid products, fissile fuel and electricity. We also furnish the results of a limited parametric analysis of the modeled reactor, illustrating the technological and economic implications of varying some important reactor design parameters.
Date:
October 12, 1977
Creator:
Bender, D.J. & Carlson, G.A.
System:
The UNT Digital Library
Hazardous waste operational plan for site 300
This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department.
Date:
February 12, 1982
Creator:
Roberts, R.S.
System:
The UNT Digital Library
Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 3. Test Evaluation. Section 2
A test was conducted on August 12 to 13, l961, on the operation of the four reactor coolant loop relief valves and the four purification system relief valves. The results indicated proper operation. (D.L.C.)
Date:
January 12, 1962
Creator:
unknown
System:
The UNT Digital Library
An analysis of grazing incidence metal mirrors in a laser ICF reactor driver
Grazing incidence metal mirrors (GIMMs) are examined to replace dielectric mirrors for the final elements in a laser beam line for an inertial confinement fusion reactor. For a laser driver with a wavelength from 250 to 500 nm in a 10-ms pulse, irradiated mirrors made of Al, Al alloys, or Mg were found to have calculated laser damage limits of 0.3--2.3 J/cm{sup 2} of beam energy and neutron lifetime fluence limits of over 5 {times} 10{sup 20} 14 MeV n/cm{sup 2} when used at grazing incidence and operated at room temperature or at 77 K. A final focusing system including mirrors made of Al alloy 7475 at room temperature or at liquid nitrogen temperatures used with a driver which delivers 5 MJ of beam energy in 32 beams would require 32 mirrors of roughly 10 m{sup 2} each. This chapter includes calculations of damage limits for GIMMs and discusses critical issues relevant to the integrity and lifetime of such mirrors in a reactor environment. The reflectivities of various metals are calculated from measured optical constants at room temperature and at cryogenic temperatures for 250- to 500-nm light at both normal and grazing incidence. Then, for the mirrors in a representative …
Date:
July 12, 1991
Creator:
Bieri, R. & Guinan, M.
System:
The UNT Digital Library
DOE Site-Specific Threat Assessment
A facility manager faced with the challenges of protecting a nuclear facility against potential threats must consider the likelihood and consequences of such threats, know the capabilities of the facility safeguards and security systems, and make informed decisions about the cost-effectivness of safeguards and security upgrades. To help meet these challenges, the San Francisco Operations Office of the Department of Energy, in conjunction with the Lawrence Livermore Laboratory, has developed a site-specific threat assessment approach and a quantitative model to improve the quality and consistency of site-specific threat assessment and resultant security upgrade decisions at sensitive Department of Energy facilities. 5 figs.
Date:
July 12, 1985
Creator:
West, D. J.; Al-Ayat, R. A. & Judd, B. R.
System:
The UNT Digital Library
HRT-CHEMICAL PLANT RUN 21 SUMMARY
The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams of solids in 10.5 hours of operation. (auth)
Date:
February 12, 1962
Creator:
Yarbro, O.O.
System:
The UNT Digital Library
GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING
The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)
Date:
December 12, 1961
Creator:
Goodman, C. D.
System:
The UNT Digital Library
Present status of the polymeric-materials screening program for the LLL geothermal project
None
Date:
June 12, 1975
Creator:
Lorensen, L.E.; Walkup, C.M. & Mones, E.T.
System:
The UNT Digital Library
SNAP 2 PRIMARY SYSTEM TEST-OBJECTIVES, SYSTEM DESCRIPTION, AND PROCEDURES
The SNAP-2 Primary System Test loop fabrication was completed with associated flight prototype components including reactor core and boiler mockups for volume and DELTA P simulation, CRU-IIII NaK pump, compact heater, and expansion compensator. A mobile loading system was designed and fabricated with the capability of cleaning the NaK prior to final loop sealing. Loop descriptions, test objectives, and operating procedures are presented. (auth)
Date:
June 12, 1961
Creator:
Kikin, G.M.
System:
The UNT Digital Library
PRELIMINARY DESIGN OF A HYDROGEN-COOLED IN-PILE LOOP FOR THE EGCR
A discussion is presented concerning the preliminary design and hazards evaluation of a H-cooled in-pile experimental loop for operation in the large double-walled through-tube in the Experimental Gas-Cooled Reactor (EGCR) at Oak Ridge. This loop is designed to permit experimentation with full-scale fuel element configurations up to 8 in. OD, at inlet gas temperatures of 600 to 950 deg F at 300 psig, and experimental power levels up to 500 kw. The results of a preliminary hazards evaluation indicate that a loop of this type can be safely operated in the EGCR. The H flammability hazard is controlled by blanketing all H-filled pipes and components with a sufficient quantity of nonreactive gas, such as He or CO/ sup 2/, to produce a noncombustible mixture for all credible H- release situations. (auth)
Date:
July 12, 1962
Creator:
Michelson, C.; Culp, A.W. & Neill, F.H.
System:
The UNT Digital Library
COOLING OF THE HFIR BERYLLIUM REFLECTOR FOLLOWING A REACTOR SCRAM OR AN ELECTRICAL POWER OUTAGE
Thermal stresses in the HFIR beryllium reflector were computed for the unlikely case where the reactor is scrammed with a simultaneous loss of coolant flow and for the case following an electrical power outage where the reactor power level and the coolant flow rate are reduced simultaneously. For the case where the reactor is scrammed with a sudden loss of the coolant flow, the resulting maximum tensile thermal stress following the scram is 22,500 psi. In case of an electrical power outage, the maximum tensile thermal stress following a reduction of the fission power level from 100 Mw to 10 Mw with the lowering of the coolant flow rate to 10% of the normal value is 12,800 psi. (auth)
Date:
December 12, 1961
Creator:
McLain, H. A.
System:
The UNT Digital Library
(Investigation of low-cost solar cells based on Cu/sub 2/O). Third quarterly progress report, November 1, 1979-January 31, 1980
Efforts this quarter concentrated on completion and check-out of the MBE system, deposition of ZnS films, analysis of the internal photoresponse for Cu-Cu/sub 2/O cells, and fabrication and characterization of Cu-Cu/sub 2/O solar cells. In-doped ZnS films with very good optical quality and finite conductivity were obtained by co-depositing In and ZnS. Analysis of the internal photoresponse indicated that minority carrier diffusion lengths on the order of 10 ..mu..m are being achieved with the present Cu/sub 2/O growth procedure. Active area values of J/sub PH/ = 8.52 mA/cm/sup 2/ and AM1 Efficiency = 1.76% were achieved for Cu-Cu/sub 2/O cells. These devices appear to have an MIS structure, or fixed charge at the interface. In particular, analysis of I-V data indicates that the current-voltage characteristics for applied voltages greater than 0.3 V are characterized by n approx. = 1 and J/sub 0/ approx. = 2 x 10/sup -9/ mA/cm/sup 2/, which implies an effective barrier height of 0.94 eV compared to the theoretical value of 0.7 eV for a Cu/Cu/sub 2/O Schottky barrier. Another very significant achievement this past quarter was the development of a surface preparation procedure which results in a nearly perfect stochiometry at the surface.
Date:
March 12, 1980
Creator:
Olsen, L. C.
System:
The UNT Digital Library
Numerical simulations of mesoscale precipitation systems. Final progress report, 1 April-30 June 1981
A numerical model designed for the study of mesoscale weather phenomena is presented. It is a three-dimensional, time-dependent model based upon a mesoscale primitive-equation system, and it includes parameterizations of cloud and precipitation processes, boundary-layer transfers, and ground surface energy and moisture budgets. This model was used to simulate the lake-effect convergence over and in the lee of Lake Michigan in late fall and early winter. The lake-effect convergence is created in advected cold air as it moves first from cold land to the warm constant-temperature lake surface, and then on to cold land. A numerical experiment with a prevailing northwesterly wind is conducted for a period of twelve hours. Two local maxima of the total precipitation are observed along the eastern shore of Lake Michigan. The results in this hypothetical case correspond quite well to the observed precipitation produced by a real event in which the hypothetical conditions are approximately fulfilled.
Date:
May 12, 1982
Creator:
Dingle, A. N.
System:
The UNT Digital Library
At-sea test validation data needed to verify the NOAA/DOE CWP Analytic Code
Test data requirements are developed in this memorandum for the one-third scale Ocean Thermal Energy Conversion (OTEC) cold water pipe (CWP) at-sea tests. A major goal of the at-sea tests is to collect sufficient data so that the National Oceanic and Atmospheric Administration (NOAA)/Department of Energy (DOE) CWP Analytic Code can be validated. The code is examined to determine the individual responses requiring verification. The wave environment is then considered for prototype survival and the scaled test. The expected response of the OTEC CWP test article in the test environment is used to form a basis of the test plan. Requirements for the tests of standard configurations of the OTEC CWP test system are first planned followed by requirements for tests of alternate configurations and evolutions. The final product is a set of justified NOAA/CWP analytic code validation requirements.
Date:
March 12, 1980
Creator:
Major, R. A.
System:
The UNT Digital Library
Water reuse achieved by zero discharge of aqueous waste
Plans for zero discharge of aqueous waste from ERDA's nuclear weapons plant near Denver are discussed. Two plants - a process waste treatment facility now under construction, and a reverse osmosis desalting plant now under design, will provide total reuse of waste water for boiler feed and cooling tower supply. Seventy million gallons of water per year will be conserved and downstream municipalities will be free of inadvertent pollution hazards.
Date:
January 12, 1976
Creator:
Kelchner, B. L.
System:
The UNT Digital Library