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RADIOACTIVE FALLOUT FROM NUCLEAR WEAPONS TESTS. Proceedings of a Conference Held in Germantown, Maryland, November 15-17, 1961
Thirty papers are presented reviewing AEC research projects related to fall-out from weapons tests. Reviews of specific related programs by representatives from Canada and the UK are also included. The scope of the conference includes characteristics of fall-out, atmospheric factors affecting deposition, distribution in the environment, and distribution in the food chain and man. Separate abstracts have been prepared for each paper. (C.H.)
Date:
February 1, 1962
Creator:
Klement, A.W. Jr. ed.
Object Type:
Report
System:
The UNT Digital Library
Studies on Lymphocytes. [Part] 1. Lymphopenia Produced by Prolonged Extracorporeal Irradiation of Circulating Blood
A method for extracorporeal irradiation of the circulating blood is described. Extracorporeal irradiation of the blood will produce a lymphopenia promptly which persists for weeks. Heparin in high doses in the calf produces a lymphocytosis and neutrophilic leukocytosis. (auth) Red cell sensitization by either agglutinating or incomplete antibodies was detected with an I/sup 131/ labeled rabbit antihuman globulin serum (RAG). Non-specific absorption of RAG by red cells was reduced to a minimum by the addition of 6% bovine albumin. The reactions between RAG and the sensitized erythrocytes were typical of antigen- antibody reactions and the sensitivity of the test was found to be greater than the standard Coombs test. Quantitative studies of the degree of erythrocyte sensitization by isoimmune or autoimmune antibodies were possible with this technic. (auth)
Date:
August 1, 1962
Creator:
Cronkite, E. P.; Jansen, C. R.; Mather, G. C.; Nielsen, N. O.; Usenik, E. A.; Adamik, E. R. et al.
Object Type:
Article
System:
The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY-MARCH 1962
Additional experiments conducted on nitridation of irradiated U-fissium fuel pins revealed that irradiation does not greatly affect the nitridation rate at 300 deg C. In skullreclamation development, a phase separation common to both the blanket- and skull-processes was investigated in which a 50% Mg-- Zn supernatant solution was removed from precipitated U metal. In most runs the supernatant phase was removed with negligible U entrainment. The reduction rate of ZrO by Zn--Mg solution under skull-recovery process conditions was found to be lower than that of U oxides. It may be possible in this process to effect some Zr separation by limiting the reduction time to that necessary for U. Methods of procesging EBR-II fuels are being investigated to establish methods of separating rare earths from Pu. Development work on preparation of UC by addition of C to U dissolved in liquid metal media showed that the limited addition of alkali metals improves C wetting and the tests showod high C-to-U ratios and high O/sub 2/ contamination; procedure and equipment improvements are being made. Studies are in progress to evaluate the compatibility of various materials with the liquid metal-salt systems contemplated for reactor fuel reprocessing. Tungsten appears to have high corrosion …
Date:
June 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
New Hot Laboratory Facilities at Los Alamos
New Hot Laboratory Facilities which support three major research programs directed by the Los Alamos Scientific Laboratory of the University of California are described. For the Nuclear Rocket Propulsion Program, a hot cell addition to the Radio Chemistry Building at Los Alamos will be completed early in 1963, and construction is expected to start soon on the hot cell addition to the Maintenance, Assembly and Disassembly Building at the Nuclear Rocket Development Station in Nevada. Integral hot laboratories are designed in the facilities for the Ultra High Temperature Reactor Experiment and the Fast Reactor Core Test at Los Alamos. (auth)
Date:
January 1, 1962
Creator:
Wherritt, Charles R.; Franke, Paul R.; Field, R. E. & Lyle, A. R.
Object Type:
Article
System:
The UNT Digital Library
COATING OF UO$sub 2$ PARTICLES WITH BeO BY SOLUTION METHODS
Spherical particles of beryllium oxide containing and enclosing UO/sub 2/ particles (-1O micron) were prepared by dispersing a suspension of UO/sub 2/ in a concentrated viscous solution of a basic beryllium saIt in a liquid organic medium, drying, and firing. The spheres produced were porous and would require densification to make the beryllium oxide protective to the UO/sub 2/. Precipitation of beryllium hydroxide or carbonate on UO/sub 2/ particles suspended in solutions of beryllium salts under various conditions produced no actual coating of the UO/sub 2/ particles. (auth)
Date:
May 1, 1962
Creator:
McDowell, W.J.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Irradiation on Uranium-Plutonium-Fissium Fuel Alloys. Final Report on Metallurgy Program 6.5.5
A total of 35 specimens of U-Pu-fissium alloy and 2 specimens of U-10 wt% Pu-5 wt% Mo alloy were irradiated as a part of the fue1-alloy development program for fast breeder reactors at Argonne National Laboratory. Total atom burnups ranged from 1.0 to 1.8% at maximum fuel temperatures ranging from 230 to 470 deg C. Emphasis was placed on the EBR-II Core-III reference fuel material, which is an injection-cast, U-20 wt% Pu-10 wt% fissium alloy. lt was found that this material begins to swell catastrophically at irradiation temperatures above 370 deg C. The ability of the fuel to resist swelling did not appear to vary appreciably with minor changes in Zr or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pourcast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated. (auth)
Date:
July 1, 1962
Creator:
Horak, J. A.; Kittel, J. H. & Dunworth, R. J.
Object Type:
Report
System:
The UNT Digital Library
Irradiation Behavior of Restrained and Vented Uranium-2 w/o Zirconium Alloy. Final Report-Programs 6.1.22 and 6.1.27
Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the …
Date:
June 1, 1962
Creator:
Horak, J. A.; Kittel, J. H. & Yaggee, F. L.
Object Type:
Report
System:
The UNT Digital Library
Kinetic Studies of the Reactions Occurring Between Tungsten and Gases at Low Pressure and High Temperatures
Oxygen, nitrogen, and nitric oxide gases were passed through a system consisting of a tungsten filament, an ion gauge, and a mass spectrometer. The ion gauge recorded total pressures and the spectrometer recorded partlal pressures of O/sub 2/, N/sub 2/, NO, CO, COa, and H/sub 2/O. From the way these pressures changed with filamert temperature, the rates of conversion of O/sub 2/ to volatile tungsten oxides and O, and of NO to volatile tungsten oxides N/sub 2/ , O/sub 2/, and O were computed. The time rate of resistance change in the filament was used to compute the rate of conversion of tungsten to tungsten oxides. The filament temperatures ranged from 1950 through 2600 deg K and gas pressures ranged from 10/sup -8/ to 10/sup -6/ atm. For the tungsten-oxygen reaction, the rates of tungsten and oxygen loss were found to depend upon oxygen atom concentration on the surface. The rate of oxide power, depending upon the concentration of oxygen atoms on the surface. The reaction rate at constant oxygen pressure decreases with increasing temperature. For calculational purposes, the tungsten oxygen gas moleeules were assumed to be WO/sub 3/ only, though WO/sub 2/ and WO are other possible products. The …
Date:
April 1, 1962
Creator:
Anderson, H. U.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
BEAM TRANSPORT. A Selected, Annotated Bibliography
References applicable to the problems of transponting charged particles in the areas external to accelerators are presented. The 891 references cover the period 1949 to 1981, with a few references both prior and subsequent to this period included. Part I is concerned with the more general aspects of electron optics. Part II contains the references that deal more directly with applications to particle accelerators. Arrangement within each pant is by broad subject with cross references listed at the end of each section. An author index is included. (M.C.G.)
Date:
August 1, 1962
Creator:
Kepple, R.R.
Object Type:
Report
System:
The UNT Digital Library
Thermodynamics of Extraction of Nitric Acid by Tri-N-Butyl Phosphate- Hydrocarbon Diluent Solutions. [Part] 2. Densities, Molar Volumes, and Water Solubilities of TBP-AMSCO 125-82-HNO*SUB 3/-H*SUB 2/0 Solutions
None
Date:
October 1, 1962
Creator:
Davis, W. Jr.
Object Type:
Article
System:
The UNT Digital Library
Periodic Characterization of Radioactive Waste Disposal System Effluents. Test Evaluation
>The major nuclides present in the Radioactive Waste Disposal System effluent water and gas were characterized. The major gamma activity in all of the liquid samples analyzed was Co/sup 60/. The ion exchangers and gas stripper removed the major activities in both particulate and filterable form and reduced the gross activity to well within limits for discharge to the environment. Sr/ sup 90/ was not detectable in the reactor plant effluent. The major activity in the Vent Gas Systems was Xe/sup 133/. Mn/sup 54/ activity was present in the Decontamination Room effluents in a ratio of 1 to 3 with Co/sup 60/. (M.C.G.)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Plutonium Fuel Processing and Fabrication for Fast Ceramic Reactors
>A study was made of the processes available for fabrication of plutonium-containing fuel from a fast ceramic reacter, and for chemical reprocessing of irradiated fuel. Radiations from recycled plutonium are evaluated. Adaptation of conventional glove-box handling procedures to the fabrication of recycle plutonium appears practical. It is concluded that acceptable costs are obtainable using moderate extensions of conventional glove- box fabrication methods and wet processing techniques, provided a significant volume of production is available. The minimum economic scale for the preferred chemical reprocessing method, anion exchange, is about 500 Mw(e) of reactor capacity. The minimum scale of economic operation for the fuel refabrication facility corresponds to three 500 Mw(e) reactors, if only steady-state refueling provides the fabrication load. The minimum volume required falls to one 500 Mw(e) reactor, if the continued growth of capacity provides fabrication volume equal to that for refueling. The chemical reprocessing costs obtained range from 0.27 mills/kwh for 1500 Mw(e) of reactor capacity, to 0.10 mills/kwh for 3000 Mw(e) of capacity. The estimated fuel fabrication cost is l/kg of uranium and plutonium in the core region (excluding axial and radial blankets) or .06/ g of plutonium content, When axial blankets, fabricated in the same rods, are …
Date:
February 1, 1962
Creator:
Zebroski, E.L.; Alter, H.W. & Collins, G.D.
Object Type:
Report
System:
The UNT Digital Library
The Preparation, Properties, and Uses of Americium-241, Alpha-, Gamma-, and Neutron Sources
A study was made of the preparation of alpha, gamma, and neutron sources using the long-lived radioisotope of americium, Am/sup 241/. Americium-241 is an artificiallyproduced radioelement which has a half-life of 462 plus or minus 10 years and decays to Np/sup 237/ by alpha emission followed by low-energy gamma emission. The high specific activity of americium-241 (7.0 x 10/sup 9/ d/m/mg) combined with its reasonably long half-life makes it ideally sulted for the preparation of radioactive sources. The chemical and physical properties of Am/ sup 241/ and the physical manipulations involved in fabricating alpha, gamma, and neutron sources are generally described in this report. Uses for each type of source are discussed and data are presented to indicate the respective properties and usefulness of each source type. (auth)
Date:
September 1, 1962
Creator:
Strain, J. E. & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
THE DISTILLATION OF URANIUM HEXAFLUORIDE AND BROMINE PENTAFLUORIDE IN A 0.5- INCH-DIAMETER PACKED COLUMN
The efficiency of a 0.5 in. dia packed column with 1/16 in. nickel helices for the separation of the binary system UF/sub 6/-- BrF/sub 5/ was investigated. Several distlllations were performed wlth the system methylcyclohexane and nheptane for purposes of callbration. For both systems, pressure-drop measurements at various flow rates were determined and the flooding rates were determined from these. Experiments to determlne the equilibrium time were also conducted with both the organic and inorganic systems used for calibration. The separation efficiency was calculated as Htu/sub g/. The flooding rates determined were 570 for methylcyclohexane, 2680 for uranlum hexafluoride, and 2200 lb/(hr) (ft//sup 2/) for bromine pentafluoride. Equilibrium times of 34 and 24 hr were found for the organic and inorganic systems, respectively. The Htu/sub g/ was found to be 1.2 in. for flows of 50 to 450 lb/(hr)(ft//sup 2/) for the organic system. The Htu/sub g/ for the inorganic system was 1.3 in. at flow rates above 285 lb/(hr)(ft/sup 2/) and was found to increase to almost 3 in. at flow rates below this. (P.C.H.)
Date:
May 1, 1962
Creator:
Ivins, R.O.
Object Type:
Report
System:
The UNT Digital Library
TABLE OF TRIM DISCRETE QUADRATURE PARAMETERS FOR THIN BINARY SLAB CELLS
Discrete quadrature weights and angles for use in discrete ordinate methods of solutions for thin cells were tabulated for a series of regional cell thicknesses of applicability. Parameters are given for 4, 8, 8, 10, and 12 angle approximations. The quadrature assignment was based upon a simplified integral transport solution to the spatial average of the angular distribution of uncollided flux, assuming flat sources. The quadrature assignments are designated TRIM, for thin-region integral method, and are most useful with thin cells having either or both regions very thin in mean-free-path units. The IBM- 704 Fortran program used to compute the parameters is described. (auth)
Date:
September 1, 1962
Creator:
Meneghetti, D.
Object Type:
Report
System:
The UNT Digital Library
A Method for Estimating the Heat of Formation and Free Energy of Formation of Inorganic Compounds
None
Date:
August 1, 1962
Creator:
Wilcox, D. E.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Final Safety Evaluation of a Ten Watt Strontium-90 Fueled Generator for a Deep Sea Application-SNAP 7E
A safety evaluation of the SNAP 7E thermoelectric generator system is described. Analyses were performed to assess the radiobiological effects in event of a fuel release and the shielding was evaluated to determine the safe working limits for personnel. The entire evaluation is based on a fuel loading of 31,000 curies of radiostrontium. It is concluded that the safety criteria are met and there is reasonable assurance that this generator is safe for its intended mission. (J.R.D.)
Date:
May 1, 1962
Creator:
Berkow, H. N. & Kelly, V. G.
Object Type:
Report
System:
The UNT Digital Library
The Generation of Poisson Time Distributed Random Pulses
The need for a source of pulses randomly distributed in time according to the Poisson distribution is discussed. A theoretical analysis showed that these pulses may be generated by employing an electrical white noise'' source. Calculations indicated the feasibility of a generator capable of producing Poisson pulse at a maximum average rate of one megacycle. The results of laboratory experiments support the calculations and demonstrate the nadequacy of using periodic pulses to determine instrument response to random pulses. A design of a nuclear signal simulator incorporating the Poisson pulse generator is suggested. (auth)
Date:
June 1, 1962
Creator:
Wilde, N.
Object Type:
Report
System:
The UNT Digital Library
SUMMARY OF HRT RUNS 22, 23 AND 24
In runs 22, 23, and 24 the HRT was operated with downward flow through the core at powers up to 5 Mw. Because of leakage past the lower core tank patch, uranium could not be prevented from entering tbe blanket, so the concentration was deliberately kept above 1 g U/kg D/sub 2/O. The core power was about 0.6 of the total. Nuclear power fluctuations were larger than with upward core flow, and the cause was investigated intensively in run 22 at powers up to 1.8 Mw. Run 22 was terminated after 778 hours when a leak developed in a fuel feed pump weld. In run 23 the power was ratsed stepwise to 5 Mw. This run was terminated after 794 hours by the removal of the fuel, containing the fission and corrosion products accumulated in 10,028 hours of operation. Fuel replacement required three days. Run 24 operations were hampered by a leak which developed between the feed and letdown streams in the fuel letdown heat exchanger. The run was terminated after 546 hours, when a crack developed in a fuel feed line tee and leaked solution into the reactor cell. The changes in the core flow and heat transfer were …
Date:
March 1, 1962
Creator:
Bauman, H.F.; Buchanan, J.R.; Engel, J.R.; Haubenreich, P.N. & Richardson, D.M.
Object Type:
Report
System:
The UNT Digital Library
HAZARD SUMMARY REPORT FOR THE ARGONNE AGN-201 REACTOR
Essential characteristics of the AGN-201 reactor facility are described. Information on personnel responsibilities and requirements is included along with an evaluation of reactor safety. (J.R.D.)
Date:
February 1, 1962
Creator:
Ruzich, K.C. & Sturm, W.J. eds.
Object Type:
Report
System:
The UNT Digital Library
THERMAL STRESSES IN HOLLOW CYLINDERS OF BERYLLIUM OXIDE
The problems of experimentally studying the effects of thermal stresses in beryllium oxide are considered in detail. Several ways of producing thermal stresses in hollow cylinders are described and the theoretical stress equations are given for these conditions. Theoretical treatment and practical considerations indicate that an experimental technique involving a static DELTA T and external heating of a hollow cylinder should be the most acceptable experimental approach. (auth)
Date:
January 1, 1962
Creator:
Swindeman, R.W.
Object Type:
Report
System:
The UNT Digital Library
Simple High-Voltage Trapezoidal Pulse Generator
A description is given of a circuit used to produce negative voltage pulses up to 60 kilovolts with a portion rising with constart slope up to 10 kilovolts per microsecond. (auth)
Date:
March 1, 1962
Creator:
Gonella, L.
Object Type:
Report
System:
The UNT Digital Library
Radiochemistry of uranium
This volume which deals with the radiochemistry of uranium is one of a series of monographs on radiochemistry of the elements. There is included a review of the nuclear and chemical features of particular interest to the radiochemist, a discussion of problems of dissolution of a sample and counting technique, and finally, a collection of radiochemical procedures for the element as found in the literature.
Date:
March 1, 1962
Creator:
Gindler, J.E.
Object Type:
Report
System:
The UNT Digital Library
The Uranium-Rich End of the Uranium-Zirconium System. Final Report- Metallurgy Program 3.1.3.
The uranium-rich end of the uranium-zirconium alloy system was reinvestigated. The solubilities of zirconium in alpha and beta uranium were found to be 0.21 wt% at 662 deg C and 0.41 wt% at 693 deg C, respectively. The monotectoid decomposition of gamma /sub 1/ at 693 deg C and the eutectoid decomposition of t 662 deg C were confirmed. For alloys containing less than 150 ppm of oxygen by weight, the gamma /sub 1/ plus gamma /sub 2/ phase region boundaries were located at 4.5 and 22.0 wt% zirconium at the monotectoid temperature. Data are given which indicate that oxygen concentrations ranging from 160 to 355 ppm by weight have a marked effect on phase relations in the area of the gamma /sub 1/ plus gamma /sub 2/ phase region. (auth)
Date:
February 1, 1962
Creator:
Zegler, S. T.
Object Type:
Report
System:
The UNT Digital Library