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Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments (open access)

Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a single-filament mass spectrometer is emphasized. (auth)
Date: June 29, 1962
Creator: Goris, P.
System: The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1962 (open access)

Chemical Processing Technology Quarterly Progress Report, January-March 1962

The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …
Date: June 29, 1962
Creator: Bower, J. R.
System: The UNT Digital Library
Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962 (open access)

Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962

The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe …
Date: June 29, 1962
Creator: unknown
System: The UNT Digital Library
BIO-ORGANIC CHEMISTRY QUARTERLY REPORT - MARCH THROUGH MAY1961 (open access)

BIO-ORGANIC CHEMISTRY QUARTERLY REPORT - MARCH THROUGH MAY1961

The study of meteorite Murray has been reported in previous Quarterly Reports. This report gives further results with Murray, and information on another meteorite, Orgueil. A sample of Orgueil was sent from the Museum National d Histoire Naturelle, Paris. It fell in several pieces over an area of 2 square miles near Orgueil, France, in 1864. The elemental analysis of this meteorite is shown in Table 1. They extracted a 10.07-g sample of this meteorite with water, using the same procedure as that for Murray. The water extracted 1.32 g, which is at least twice as much material as was water-extracted from Murray. The elemental analysis of the water extract is given in Table II and its uv spectrum is shown in Figure 1. From an x-ray diffraction pattern it was determined that the water extract contained mostly MgSO{sub 4} {center_dot} 6H{sub 2}O with some calcium sulfate. Their spectrum (Figure 2) shows a strong SO{sub 4} band at 1100 cm{sup -1}, = strong H{sub 2}O bands at 1650 cm{sup -1} and 3200-3600 cm{sup -1}, and some unidentified peaks at 2300, 1400, and 980 cm{sup -1}. The approximately 8 g of Orgueil left after the water extraction was then extracted with …
Date: June 29, 1961
Creator: unknown
System: The UNT Digital Library
IBM Problem M Curves (open access)

IBM Problem M Curves

Abstract: Presented here are working graphs of pressure, density, velocity, and temperature from the Los Alamos Scientific Laboratory calculations (IBM Problem M) of a spherically symmetric explosion in a homogeneous atmosphere.
Date: June 29, 1960
Creator: Broyles, C. D.
System: The UNT Digital Library
Synthesis and Fabrication of Refractory Uranium Compounds. First Quarterly Report, March 1 Through May 31, 1961 (open access)

Synthesis and Fabrication of Refractory Uranium Compounds. First Quarterly Report, March 1 Through May 31, 1961

Activities in a program to obtain UC pellets of maximum density for irradiation testing are described. A study was made of the effects of the UC powder thermal history, sintering time, sintering temperature, and additives on the UC sinterability. Preliminary results indicate that the UC powder synthesized under the most severe conditions of temperature and time (1740 deg C, 107 min) was less sinterable than powders prepared at lower temperatures, or at the same temperature for shorter time. It was also concluded that although both temperature and time of sintering pellets affect density, temperature is more important. Additions of Fe (0.1 to 1.0%) improve sinterability and promote grain growth. The final density obtained on sintering in a vacuum was about the same as that resulting from sintering in He at atmospheric pressure. (J.R.D.)
Date: June 29, 1961
Creator: Taylor, K. M. & McMurtry, C. H.
System: The UNT Digital Library
Internal instrumentation cable transitioning (open access)

Internal instrumentation cable transitioning

None
Date: June 29, 1965
Creator: Chambers, G.M.
System: The UNT Digital Library
FEASIBILITY STUDY FOR INPLACE ANNEALING OF THE PM-2A REACTOR VESSEL (open access)

FEASIBILITY STUDY FOR INPLACE ANNEALING OF THE PM-2A REACTOR VESSEL

None
Date: June 29, 1962
Creator: Medal, E.
System: The UNT Digital Library
MOUND LABORATORY PROGRESS REPORT FOR JUNE 1962 (open access)

MOUND LABORATORY PROGRESS REPORT FOR JUNE 1962

Research and development progress is reported on plastics, analytical methods, radioelements, isotope separation and purification, reactor fuels and materials developmert, Ranger x-ray sensor program, and SNAP a. (M.C.G.)
Date: June 29, 1962
Creator: Grove, G.R.; Jones, L.V. & Eichelberger, J.F.
System: The UNT Digital Library
A NEW SOURCE OF SMALL-ANGLE X-RAY SCATTERING (open access)

A NEW SOURCE OF SMALL-ANGLE X-RAY SCATTERING

None
Date: June 29, 1965
Creator: Perret, R G & Keating, D T
System: The UNT Digital Library
Solubilities of Selected Metals in Mercury: Hermex Process (open access)

Solubilities of Selected Metals in Mercury: Hermex Process

The solubilities of uraninm, thorium, gadelinium, sama rinm, and neodymium in mereury were determined from room temperatare to 356 deg C. Equations of the form log of solubility (wt.%) = a + b/T were developed for these metals. Integral heats of solution were calculated for each. The solubilities of ruthenium, palladium, zirconium, and molybdenum in mercury in the presence of excess uranium were determined; the low solubility of zirconium and molybdenum gave solutions with a concentration below the limit of detection in the analytical method used. Their values are reported as an upper solubility limit. Uranium solubility in a 0.1 wt.% magnesium amAlgam was approximately 1.2 to 1.5 times greater than in mercury alone. When uranium and thorium were present in the same mercury solution, their solubilities were mutually depressed. (auth)
Date: June 29, 1960
Creator: Messing, A. F. & Dean, O. C.
System: The UNT Digital Library
Corrosion Status: Sulfex-Thorex (Ni-O-Nel) and Darex-Thorex (Titanium) as of June 12, 1959 (open access)

Corrosion Status: Sulfex-Thorex (Ni-O-Nel) and Darex-Thorex (Titanium) as of June 12, 1959

Current results indicate probable over-all rates of about 0.2 mils/month for titanium vs. 1.5 to 3.0 mils/month for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but they have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques. There is a possibility that a Ni-onel dissolver could be used for interim Zirflex processing although the rates obtained in scouting tests are relatively high (6 to 8 mils/month). Titanium shows no promise of usefulness in either Zirflex or Sulfex on the basis of scouting tests. It can be used for dissolution of U-Al fuels in 8M HNO/sub 3/- Hg(N0/sub 3/)/sub 2/ (rate < 1 mil/month). If the choice between these two processes were made on the basis of present corrosion results alone, Darex-Thorex would be chosen. (auth)
Date: June 29, 1960
Creator: Clark, W E
System: The UNT Digital Library
Isostatically molded P-03 graphite for large structures (open access)

Isostatically molded P-03 graphite for large structures

None
Date: June 29, 1965
Creator: Kachur, V. & Nicholson, H.C.
System: The UNT Digital Library
Letter to J. S. Kelley, AEC on the Project Sulky Concept (open access)

Letter to J. S. Kelley, AEC on the Project Sulky Concept

This letter provides information on a proposed peaceful use of nuclear explosives (Project Sulky)with regard to nuclear excavation for an Isthmian canal. Nuclear explosion detection, radioactivity release, details of the changes in the experimental plan, and Pike venting analysis are included.
Date: June 29, 1964
Creator: Johnson, G. W.
System: The UNT Digital Library
Annotated Bibliography on Soft X-ray Spectroscopy (open access)

Annotated Bibliography on Soft X-ray Spectroscopy

Report presenting a bibliography of about 550 references of the soft X-ray literature since 1950 and through 1960. The emphasis is on the application of soft X-ray spectroscopy to the study of valence band electronic states in metals and alloys. Therefore, the spectral region of 25 to 800 angstroms involving ruled glass grating spectrometers is of principal interest. In addition to soft X-ray data, references on all pertinent aspects of the apparatus and experimental problems are included. Also listed separately are references of value in corroborating soft X-ray data with other results. Subject, author, X-ray band, material, and other indices are included.
Date: June 29, 1962
Creator: Yakowitz, Harvey, 1939- & Cuthill, J. R.
System: The UNT Digital Library
Status of irradiations performed by testing for BNW as of June 11, 1967 (open access)

Status of irradiations performed by testing for BNW as of June 11, 1967

This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.
Date: June 29, 1967
Creator: DeMers, A. E.
System: The UNT Digital Library
Thermal Analysis of SM-1 Core III (open access)

Thermal Analysis of SM-1 Core III

Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition.
Date: June 29, 1962
Creator: Davidson, S. L.
System: The UNT Digital Library