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Chemical Processing Department Monthly Report
11
Hanford Works Monthly Report
3
Fiscal Year 1997
2
Fiscal Year 2005
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Fiscal Year 2008
2
Irradiation Processing Department Monthly Record Report
2
Mound Laboratory Monthly Health Information Report
2
Notes of Monthly Component Test Program Review Meeting Held with SNPO at WANL
2
Annual Illness and Injury Surveillance Report
1
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WELDING AND BRAZING OF HIGH-TEMPERATURE RADIATORS AND HEAT EXCHANGERS
Procedures were developed for fabricating highperformance radiators and heat exchangers for the Aircraft Nuclear Propulsion (ANP) Program. These components, which contain multitudes of tube-to-tube sheet and tube-to-fin joints, are similar in design to those under consideration for a variety of space vehicle applications. In order to ensure reliability of the tube-to-tube sheet joints, techniques producing welds of extremely high quality were used and back brazing of the welds with a suitable alloy was incorporated. High-temperature brazing was also incorporated to attach high-conductivity fins to Inconel tubes in the radiators. The selection of a suitable brazing alloy for these applications was dependent upon several factors, including corrosion and oxidation resistance, flow point, and mechanical properties. A Ni- Si-B alloy was found to be adequate from all these considerations. Special brazing procedures were developed to obtain satisfactory flowability of this brazing alloy on tube-to-fin joints. The suitability of these fabrication procedures for the very stringent service conditions to which the radiators and heat exchangers were subjected was demonstrated by testing full-size components under operating conditions. (auth)
Date:
February 20, 1962
Creator:
Slaughter, G.M. & Patriarca, P.
System:
The UNT Digital Library
Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix A: mission analysis and performance specification studies. Volume I
Studies are described which were performed for the Near Term Hybrid Vehicle program to determine passenger car usage patterns and to correlate these trip mission characteristics with vehicle design and performance specifications. (LCL)
Date:
April 20, 1979
Creator:
Traversi, M. & Barbarek, L.A.C.
System:
The UNT Digital Library
Mixing and Evaporation in a Packed Vessel
In connection with an evaluation of the operability of a 36-inch diameter remote evaporator at the Idaho Chemical Processing Plant that was to be packed with a corrosionresistant neutron-poison packing for criticality control, an investigation in a 30-inch diameter vessel proved that air sparging effectively mixes solutions. The data showed that at similar spar;e rates the presence of the packing caused an increase in the time needed for complete mixing. The investigation showed that solutions are readily evaporated in spite of the presence of packing in the tank. (auth)
Date:
September 20, 1961
Creator:
Cederberg, C. K. & Buckham, J. A.
System:
The UNT Digital Library
Repair Welding of Fusion Reactor Components
Recent experimental investigations indicate that the repair welding of irradiated materials containing greater than 1 to 2.5 appm helium leads to catastrophic cracking in the heat affected zone of the weld. The high temperatures and cooling tensile stresses which occur during the welding process lead to enhanced helium bubble growth in the heat affected zone region, resulting in catastrophic cracking upon cooling. An investigation is proposed which seeks to determine the effect of stress state on the helium bubble growth process and develop engineering modifications to the welding process based upon this understanding in an attempt to alleviate or eliminate the weld cracking problem in type 316 stainless steel materials.
Date:
May 20, 1992
Creator:
Chin, Bryan A.
System:
The UNT Digital Library
Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor
The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, formed on the water-cooled aluminum surfaces during test. When only relatively thin films formed, the boehmite adhered tightly to the aluminum, but in those cases where relatively thick films formed, some boehmite spontaneously spalled from the surface. The rate at which the boehmite formed on the surface (and consequently the rate at which the aluminum temperature increased) was a function of the temperature at the specimen-water interface and the pH of the coolant. The lower the temperature and the lower the pH (in the range of 5.0 to 6.5 with HNO/sub 3/), the lower the rate of corrosion- product formation. Within the ranges investigated, pressure and flow rate were without effect, and the same results …
Date:
December 20, 1961
Creator:
Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L.
System:
The UNT Digital Library
Cross Sections for X-Ray Photoelectron-Induced Desorption of Hydrogen Ions From Metal Surfaces
We have measured the cross sections for x-ray photoelectron-induced desorption of hydrogen ions from beryllium, carbon, aluminum, tantalum, and gold surfaces. This report describes the results of the cross-section measurements, and discusses a time-of-flight technique that allows the determination of ionic-desorption cross sections as small as 10/sup -25/ cm/sup 2/ per photoelectron. 19 refs., 7 figs.
Date:
September 20, 1985
Creator:
Kinney, J. H.; Siekhaus, W. J. & Anderson, R. A.
System:
The UNT Digital Library
Development of passive electronic components for instrumentation of improved geothermal logging tools and components. Annual progress report
Short term objectives for well-logging instrumentation are circuits which can operate at temperatures in the range 275/sup 0/C to 350/sup 0/C; the medium term goal is operation up to 500/sup 0/C, and the long term goal is to achieve operation at 1000/sup 0/C. It is apparent that useful electronic circuits will require the combination of both passive components and active devices. In order to meet the compatibility requirements, the basic technology which has been selected in this project is the chemical vapor deposition of metal interconnections, resistor material, dielectric material and passivating material. It is to be emphasized that this is a thin-film, not thick-film, technology which is compatible with the processing methods used in fabricating either semiconductor or integrated thermionic devices, and produces components which are electrically compatible with those devices. The investigation in this project is primarily directed toward tungsten metallization, tungsten-silicon resistors, and silicon nitride dielectric and passivation.
Date:
October 20, 1977
Creator:
Raymond, L.S.; Hamilton, D.J. & Kerwin, W.J.
System:
The UNT Digital Library
In Vivo Gamma Lung Measurements--a Mathematical Model
A low-background facility is described for rneasuring lung burdens of U, Th, and other nuclides in vivo. Problems associated with this method of radiation measurement are discussed. A mathennatical, computer-oriented simulation was devised to gain insight into the relation of the net observed radiation spectrum to the burden of radioactivity in the body or its organs. Chest cavities for persons of three sizes were synthesized in a three-coordinate space comprised of one-inch cubes and including a 9-in.-diameter crystal detector. Data, describing the tissue composition of each cube in the body and the characteristic radiation attenuation for each tissue-type, were coded for use with a program on a high-speed digital computer. Efficiencies for measuring radiation emitted by numerous point sources of enriched uranium were calculated. Data on in vivo measurement efficiency were obtained assuming uniform distribution of radioactive material throughout the lungs and also for nonuniform deposits. The effects of individual size and geometry, and of detector position on the measurement efficiency were determined for these twvo categories and radiation flux distributions on the detector face were computed in some cases. Data are appended and a flow diagram of the computer program is included. (C.H.)
Date:
October 20, 1961
Creator:
Ammann, P. R.; Wilson, C. W. & Mohr, C. M.
System:
The UNT Digital Library
Exact calculations of nuclear-recoil energies from prompt gamma decays resulting from neutron capture
The results of an accurate determination of the recoil spectrum from (n, ..gamma..) reactions in molybdenum are presented. The recoil spectrum has been calculated from nuclear level structure data and measured branching ratios. Angular correlations between successive gammas have been accounted for using the standard theoretical techniques of Racah algebra and the density matrix formalism.
Date:
July 20, 1981
Creator:
Kinney, J.H.
System:
The UNT Digital Library
Coal fracture measurements using in situ electrical methods: preliminary results
None
Date:
November 20, 1974
Creator:
Lytle, R.J.; Laine, E.F. & Lager, D.L.
System:
The UNT Digital Library
SEPARATION OF TRANSPLUTONIUMS FROM LANTHANIDES BY TERTIARY AMINE EXTRACTION
None
Date:
December 20, 1961
Creator:
Baybarz, R.D. & Weaver, B.
System:
The UNT Digital Library
Internal dosimetry technical basis manual
The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.
Date:
December 20, 1990
Creator:
unknown
System:
The UNT Digital Library
Facile reaction/extraction of coal with supercritical fluids. Quarterly technical progress report, January 1-March 31, 1984
Arylmethyl phenyl ethers undergo competing reactions when treated with Lewis acids in benzene solvent. Apparently, benzene is insufficiently reactive to compete with intramolecular (intrapolymer) nucleophiles and, consequently, no increase in solubility accompanies the cleavages of ether links upon addition of benzene. When better nucleophiles, naphthalene and phenanthene, are provided, carbonium ions generated from ether cleavages are capped and the product is lower in molecular weight and more soluble. It is worth noting that the naphthalene (k/sub rel/ = 300) is nearly as good a trap as the phenol (k/sub rel/ = 450). Since hydroxylic solvents will level the acid strength of BF/sub 3/ to that of ROBF/sub 3//sup -/H/sup +/ and hydrocarbons would not, the acid-catalyzed bond cleavages necessary for unlinking coal may in fact be faster in BF/sub 3/-arene than in BF/sub 3/-phenol. While we have not yet extended these results to coals, we believe that the combination of a relatively mild Lewis acid catalyst, BF/sub 3/, with a good carbonium ion trap, naphthalene, will allow selective cleavage and capping of aryl alkyl ether bonds. 3 references, 2 figures, 3 tables.
Date:
April 20, 1984
Creator:
Venier, C. G. & Squires, T. G.
System:
The UNT Digital Library
MHD compressor---expander conversion system integrated with GCR inside a deployable reflector
This work originates from the proposal MHD Compressor-Expander Conversion System Integrated with a GCR Inside a Deployable Reflector''. The proposal concerned an innovative concept of nuclear, closed-cycle MHD converter for power generation on space-based systems in the multi-megawatt range. The basic element of this converter is the Power Conversion Unit (PCU) consisting of a gas core reactor directly coupled to an MHD expansion channel. Integrated with the PCU, a deployable reflector provides reactivity control. The working fluid could be either uranium hexafluoride or a mixture of uranium hexafluoride and helium, added to enhance the heat transfer properties. The original Statement of Work, which concerned the whole conversion system, was subsequently redirected and focused on the basic mechanisms of neutronics, reactivity control, ionization and electrical conductivity in the PCU. Furthermore, the study was required to be inherently generic such that the study was required to be inherently generic such that the analysis an results can be applied to various nuclear reactor and/or MHD channel designs''.
Date:
April 20, 1989
Creator:
Tuninetti, G. (Ansaldo S.p.A., Genoa (Italy). Research Div.); Botta, E.; Criscuolo, C.; Riscossa, P. (Ansaldo S.p.A., Genoa (Italy). Nuclear Div.); Giammanco, F. (Pisa Univ. (Italy). Dipt. di Fisica) & Rosa-Clot, M. (Florence Univ. (Italy). Dipt. di Fisica)
System:
The UNT Digital Library
Energy Exchange Within Ecosystems Annual Report: 1976
None
Date:
September 20, 1975
Creator:
Gates, David M.
System:
The UNT Digital Library
Administration of ORNL Research Reactors
Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date:
August 20, 1962
Creator:
Casto, W. R.
System:
The UNT Digital Library
Leaching study of PNL 76-68 glass beads using the LLNL continuous-flow method and the PNL-modified IAEA method. Final report
Lawrence Livermore National Laboratory (LLNL) has conducted a long-term single-pass continuous-flow (SPCF) leaching test of the glass waste form PNL 76-68. Leaching rates of Np, Pu, and various stable elements were measured at 25/sup 0/ and 75/sup 0/C with three different solutions and three different flow rates. The purposes of the study were: (1) to compare SPCF leaching results with the results of a modified IAEA leach test performed by Pacific Northwest Laboratories (PNL); (2) to establish elemental leach rates and their variation with temperature, flow rate and solution composition; and (3) to gain insight into the leaching mechanisms. The LLNL and PNL leach tests yielded results which appear to agree within experimental uncertainties. The magnitude of the leach rates determined for Np and the glass matrix elements is 10/sup -5/ grams of glass/cm/sup 2/ geometric solid surface area/day. The rates increase with temperature and with solution flow rate, and are similar in brine and distilled water but higher in a bicarbonate solution. Other cations exhibit somewhat different behavior, and Pu in particular yields a much lower apparent leach rate, probably because of sorption or precipitation effects after release from the glass matrix. After the initial few days, most elements …
Date:
August 20, 1982
Creator:
Buddemeier, R. W.; Coles, D. G.; Mensing, R. W.; Rego, J. & Weed, H. C.
System:
The UNT Digital Library
Summary data for U. S. commercial nuclear power plants in the United States
A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables.
Date:
March 20, 1978
Creator:
Heddleson, F.A.
System:
The UNT Digital Library
THE HEAT CAPACITY OF BERYLLIUM CARBIDE POWDER IN STAINLESS STEEL CAPSULES AS A FUNCTION OF TEMPERATURE (400-1800 F)
The mean heat capacity of a sample of powdered beryllium carbide, a possible moderator material for a nuclear reactor, was determined as a function of temperature. A thin-walled stainless steel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter. The following linear equation for mean heat capacity over the temperature range 50 f C-T f C as a function of temperature, T, was derived from the data by the method of least squares: C/sub p/ = 0.299 + 2.16 x 10/sup -4/ T f C el temperatures 0.005 cal gm/sup -1/( f C)/sup -1/. The numerical value of C/sub p/ expressed by this equation is also equal to the mean heat capacity in Btu lb/sup -1/( f F)/sup -1/. (auth)
Date:
April 20, 1949
Creator:
Powers, H.; Kostigen, T. & Trice, J.B.
System:
The UNT Digital Library
REPORT ON GLOVE BOXES AND CONTAINMENT ENCLOSURES
Criteria and guide lines are presented for the design, construction, and operation of safe, economical, and efficient glove boxes and associated facilities based upon present conditions and anticipated changes. Comprehensive discussion of glove box materials and components, safety and fire prevention methods, health physics problems, operational considerations, and brief descriptions of AEC installations are included. (39 references) (C.H.)
Date:
June 20, 1962
Creator:
Garden, N.B. ed.
System:
The UNT Digital Library
Low temperature, sulfur tolerant homogeneous catalysts for the water-gas shift reaction
The purpose of this report is to update and reorganize our recent review on homogeneous catalysis of the water-gas shift reaction (WGSR) based on recent literature publications and patents. This updated version will serve as a means of selecting 10 candidate catalyst systems for use in developing effective, sulfur-tolerant, low temperature WGSR catalysts. This report discusses the variations possible in the basic chemistry associated with WGSR catalytic cycles, including basic, acidic, and neutral conditions. Then individual mechanism for specific WGSR catalyst systems are discussed. Finally, on the basis of the literature reports, a list is presented of candidate catalysts and basic systems we have chosen for study in Task 3.
Date:
January 20, 1986
Creator:
Laine, R. M.
System:
The UNT Digital Library
Research in radiation monitoring survey instrumentation. Final report
Two low-power solid-state prototype readout units were developed, an LED display and a LCD display. This display output was in a bar-graph format, covering four-decades of information, with 10-segments per decade. The displays accept a frequency input, which is standardly available from several portable radiation-survey instruments. Both readout units will operate on two D-cell batteries (3.0 Volt), with a typical current drain requirement of 0.3 MA for the LED display and 30..mu..A for the LCD display. A wide-range electrometer circuit was also developed. The circuit covers an input current range from 10/sup -13/ A to 10/sup -8/ A. The output signal is a pulse whose frequency is directly proportional to input current. The circuit requires no high-megohm resistors, and is autoranging. Several candidate input amplifiers were analyzed and evaluated for use with the electrometer circuit.
Date:
January 20, 1978
Creator:
Blalock, T. V.; Kennedy, E. J.; Phillips, R. G. & Walker, E. W. Jr.
System:
The UNT Digital Library
MTR Fast Neutron Flux Measurements for Cycle 146
The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date:
March 20, 1962
Creator:
Weber, L. D. & Hogg, C. H.
System:
The UNT Digital Library
Cooling water for SSC experiments: Supplemental Conceptual Design Report (SCDR)
This paper discusses the following topics on cooling water design on the superconducting super collider; low conductivity water; industrial cooling water; chilled water systems; and radioactive water systems. (LSP)
Date:
October 20, 1989
Creator:
Doyle, R.E.
System:
The UNT Digital Library