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40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962

Description: Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken, a value of 0.02 VC/cm/sup 3/ was obtained for the gross activity of the primary loop. Element III-A, which was removed from the loop after generating 133 Mw-hr of fission heat, was disassembled and examined. No fuel-compact damage of any type was visible. Determination of the distribution of fission products in the element is under way, Fissionproduct- release data for in-pile-loop element III-A were calculated. During the 133 Mw- hr of operation, the release fraction increased by approximately one order of magnitude. Also calculated were the xenon and krypton release data for the first 100 Mw-hr of III-B operation. The release rate for the longer-lived isotopes increased bv about a factor of 10 and that of the shorter-lived isotopes by about a factor of 100. A test was run in which the in-pileloop purge flow, was stopped. The primariy-loop activity level rose sharply during the first hour, increased at a slower rate for the next 11 hr, and then appeared to level off. When purge flow was resumed, the gross activity in the primary loop was cleaned up with a half life of about 2.2 hr. An attempt was made to identify Cs/sup 137/ and Ba/ sup 140/ plateout in portions of the in-pile loop. A very small amount of cesium (less than a monolayer) was found, but no barium could be detected. The validity of two …
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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ACTIVITY RELEASE FROM THE N.S. SAVANNAH IN THE MAXIMUM CREDIBLE ACCIDENT

Description: The release of fission products that would occur following the maximum credible accident aboard the N.S. Savannah has been examined. Four significantly different, but realistic, operating histories were considered. The rate of release of noble gases and of iodine isotopes as a function of time after the accident was determined for each operating history and for both normal and emergency reactor-compartment ventilation systems. The influence of radioactive decay and of the time delay in release and transport of activity through the containment system was investigated. Most of the results are expressed in terms of activity release and resultant individual exposures, although some consideration is given to population exposures and to the interpretation of these results in the light of stationary reactor site criteria. (auth)
Date: October 16, 1963
Creator: Anderson, T. D.; Buchanan, J. R.; Cottrell, W. B.; Fontana, M. H.; Klepper, O. H. & McCurdy, H. C.
Partner: UNT Libraries Government Documents Department
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AEC Aerospace Safety Programs and Philosophy

Description: Work in aerospace safety analysis, research, development, and testing is discussed. Studies for the SNAP program are outlined. The engineering andd test program for aerospace safety ls described. (M.C.G.)
Date: October 1, 1963
Creator: Pittman, F. K.
Partner: UNT Libraries Government Documents Department
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Aerospace Nuclear Safety: October 1 - 4, 1963

Description: Proceedings on aerospace nuclear safety.
Date: October 1963
Creator: Sandia Corporation. Technical Information Division III.
Partner: UNT Libraries Government Documents Department
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AGS Performance and Plans

Description: The scope of the AGS complex has expanded rapidly during the three years since an accelerated beam was first obtained. Demand for research time far exceeds the amount available although facilities have been much increased. At the same time, experiments are being designed which are more complicated than previous ones and which make more stringent demands on the accelerator and on its auxiliary equipment. There is a continuous trend of experiments to particle beams of greater momentum, as the experimental techniques are refined. This use of increased momentum means that larger areas are required for the apparatus and that more power is necessary for the magnetic optics. All beam-sharing at the AGS is done by multiple use of each accelerated pulse because our experience indicates that pulse-by-pulse beam-sharing is relatively inefficient. (Expansion chambers have seldom been used at the AGS.) The problems of scheduling experiments becomes increasingly complex since combinations must be found satisfying the criteria: maximum number of experiments to run simultaneously; minimum downtime to be taken for rearrangement between successive experimental arrays
Date: October 15, 1963
Creator: Green, G. K.
Partner: UNT Libraries Government Documents Department
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ANNUAL REPORT, JULY 1, 1962

Description: The research and development work is reported in sections on physical sciences and engineering, life sciences, and supporting activities. Separate abstracts were prepared for each of these sections. (J.R.D.)
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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Apparatus for the Gasometric Study of Solid-Gas Reactions: Sodium Fluoride With Hydrogen Fluoride and Uranium Hexafluoride

Description: A gasometric apparatus for rapidly characterizing dissociation pressures, sorption equilibrium and kinetics, chemical states, and decomposition conditions was built and tested. The method involves the measurement of quantities of gases reacting with or evolving from known quantities of solid. Accuracies of better than plus or minus 1% were attained. In testing the capabilities of tue apparatus, the dissociation pressures of hydrogen fluoride and uranium hexafluoride over their respective complexes with sodium fluoride, and the decomposition of the uranium hexafluoride complex to give elemental fluorine were verified. Additionally, a test for sorption of uranium hexafluoride on sodium fluoride was developed, the existence of the compound Na/ sub 2/UF/sub 8/ was demonstrated, a more active form of sodium fluoride was made, the stability of the pentavalent uranium-- sodium fluoride complex was studied, data leading to a postulated new compound (NaF)/sub 2/(UF/sub 6/)(HF) was obtained, and the interaction of hydrogen fluoride and uranium hexafluoride on sodium fluoride was studied. (auth)
Date: October 29, 1963
Creator: Katz, S.
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1962

Description: The environmental monitoring data processed during 1962 indicated that Laboratory operations did not contribute appreciably to the contamination of the environment with radioactive materials. However, the effects of airborne radioactive materials generated from nuclear weapons tests conducted at various locations throughout the world continued to be reflected in certain parts of the environmental monitoring data. The concentration of radioactive materials in air (as determined by air filtration techniques) increased by a factor of about 2.5. The concentration of radioactive materials in rain water increased by a factor of 3 to 5. The Sr/sup 90/ concentration in raw milk increased by a factor of about 3. The I/sup 131/ concentration in raw milk increased by a factor of about 12. The general radiation background increased by a factor of 2 in the East Tennessee Area. Gamma measurements taken over river bottom sediment increased by a factor of about 2 in Fort Loudoun Reservoir, a body of water that is fed by the Tennessee River and not affected by liquid waste releases originating from Oak Ridge operations. The calculated average concentration of radioactive materials in the Clinch River resulting from waste releases originating from ORNL operations decreased from 18% of the (MPC)w in 1961 to 7.4% of the (MPC)w in 1962. The measured concentration at a point about 16 miles below the entry of ORNL waste releases averaged 4.9% of the (MPC)w during 1962. There were no personnel exposures recorded during 1982 which exceeded maximum permissible levels. The highest total body dose recorded was 4.8 rem which is 38% of the maximum permissible annual dose. There were no cases involved where the internal deposition of radioactive material in the body was estimated to have exceeded one- half of a maximum permissible body burden averaged over a l2-month period. As of December 31, …
Date: October 1, 1963
Creator: Hart, J.C. ed.
Partner: UNT Libraries Government Documents Department
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Applied Mathematics Division Summary Report, July 1, 1961-June 30, 1962

Description: A summary of each computer program initiated during the report period is given. Over 130 programs are described briefly. Work is also being carried out on the completion of the GEORGE-FLIP Computer system and the development of retrieval and pattern recognltion systems. (M.C.G.)
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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ARGONNE NATIONAL LABORATORY RADIOLOGICAL ASSISTANCE TEAM

Description: ABS>The organization, training, equipment, and operation of a radiological assistance team are described. The team renders assistance in the event of incidents involving radiological safety or weapons incidents. (C.H.)
Date: October 1, 1963
Creator: Lonergan, G.T. & Smith, W.H.
Partner: UNT Libraries Government Documents Department
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THE BERKELEY HIGH-ENERGY PHYSICS STUDY AT THE ERNEST O. LAWRENCE RADIATION LABORATORY, BERKELEY, CALIFORNIA, JUNE 15 THROUGH AUGUST 15, 1961

Description: Seminar talks and special reports presented by the Berkeley summer study group are compiled. Included in the compilation are 24 seminar talks, 10 reports, a summary of theoretical conclusions, and comments on experimental questions. Separate abstracts have been prepared for 18 seminar talks and all of the reports. Five seminar talks have been abstracted previously in NSA. (M.P.G.)
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. June through August1963

Description: This report covers the following titles: (1) The Effects of 8-Methyl Lipoic Acid on the Evolution of Oxygen and Reduction of Carbon Dioxide during Photosynthesis; (2) Further {sup 14}C and {sup 15}N Tracer Studies of Amino Acid Synthesis during Photosynthesis by Chlorella Pyrenoidosa; (3) Two-Dimensional High Voltage, Low-Temperature Paper Electrophoresis of {sup 14}C-Labeled Products of Photosynthesis with {sup 14}CO{sub 2}; (4) A Search for Enzymic and Nonenzymic Reactions Between Thiamine Derivatives and Sugar Phosphates; (5) The Cytochrome Content of Purified Spinach Chloroplast Lamellae; (6) The Osmium Tetroxide Fixation of Chloroplast Lamellae; (7) Kinetics of Exoenzymes and Applications to the Determination of the Sequence of Nucleic Acids; (8) Brain Biochemistry and Behavior in Rats; (9) Experiments on Classical Conditioning and Light Habituation in Planarians; (10) Operant Conditioning in Planarians; (11) Manganese Porphyrin Complexes; (12) EPR Studies of Some Complex Organic Solutions; (13) Transient Response of Light-induced Photosynthetic Electron Paramagnetic Resonance Signals: Rhodospirillum rubrum Chromatophores; (14) Studies of the Tautomerism of Amides; (15) Structure and Mechanism of Hydrolysis of the Product of Reaction of PZ05 and Ethyl Ether; (16) A Study of the Irradiation Products of Several Nitrones; (17) Biosynthesis of the Opium Alkaloids; (18) Synthesis of methyl-{beta}-D-thiogalactoside-{sup 35}S; (19) Effect of Acridine Orange and Visible Light on Thymine Dimer Formation and Disruption; (20) Some Aspects of the Radiation Chemistry of DNA; (21) Nuclear Magnetic Resonance; and (22) Studies on the Inhibition of the Photoreduction of FMN.
Date: October 2, 1963
Partner: UNT Libraries Government Documents Department
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Ceramic to Metal Seals for High-Temperature Thermionic Converters

Description: A rather broad investigation was carried on in the materials and methods which are considered possibly useful in forming ceramic to metal seals and composite structures for use in the environment of cesium-plasma thermionic converters. Initially, studies of five specific meands of joining refractory metals to alumina were undertaken, as well as studies of metallizing methods, of forming graded tungsten-alumina composites, and of the possible metals and ceramics which could be utilized best in structures operated at 2000 deg C. The five joining methods studied are: (1) Formation of a continuous electroplated layer of refractory metal across the adjacent surfaces of metal and ceramic. (2) Welding of a metal member to the ceramic by ultrasonic welding techniques; i.e., without heat. (3) Use of high temperature brazing alloys. (4) Formation of a bond between metal and ceramic by the diffusion of compatible intermediate materials into both structural members. (5) Welding of single oxide ceramics directly to refractory metals using electron-beam welding equipment. The study of metallizing methods was started because the first three of the joining methods listed require the use of a metallized surface of the alumina. It was determined that three of the five methods for joining refractory metals to alumina which were under study were not practically fessible. The methods considered impractical are: formation of a continuous electroplated joint, welding by ultrasonic energy, and welding with electron beam techniques. The studies on these methods were ended. Significant achievements have been made in the other studies. A metallizing process has been developed by which a strongly adherent sintered tungsten film can be applied to commercially available, high-purity, silica-free alumina. No fluxing materials or active metals which are susceptible to attack by cesium are used in this process. Bonding of alumina to molybdenum has been successful by several methods developed …
Date: October 1, 1963
Creator: Dring, M. L.
Partner: UNT Libraries Government Documents Department
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Ceramics Research and Development Operation Quarterly Report, October- December 1962

Description: CERAMICS RESEARCH AND DEVELOPMENT OPERATION QUARTERLY REPORT, OCTOBERDECEMBER 1962. Pu/sub 2/S/sub 3/ melted congruently at 1725 450 deg C in a 10 un. Concent 85% C under vacuum or argon and was stable to 2300 un. Concent 85% C in argon. Pu/sub 2/S/sub 3/ was not attacked by boiling, demineralized water. PuN melted congruently at 2750 450 deg C in a 75 un. Concent 85% C under nitrogen (1 atm), but dissociated at 2600 un. Concent 85% under argon or helium. Plutonium carbides and oxides of various compositions were formed by inert gas sintering of pressed mixtures of PuO/sub 2/ and graphite powder. Spontaneous lattice expansion of PuC at about 0.02% per month occurred over periods extending to 15 months, with no apparent saturation. PuO/sub 2/ and MgO were immiscible in all proportions and form no compounds stable at room temperature. ThO/sub 2/ was soluble in UO/sub 2/ in all proportions, although the solution was not ideal as shown by minima in both melting point versus composition and lattice parameter versus composition curves. Small additions of PuO/sub 2/ enhanced the sinterability of ThO/sub 2/. Melting points of (Th,Pu)O/ sub 2/ solid soiutions were constant below 25 wt% ThO/sub 2/. Lattice parameters of the solid solution obeyed Vegard's law. A series of tungsten-UO/ sub 2/ cermets was fabricated by high-energy-rate impaction. The tungsten matrix was uniform and continuous at UO/sub 2/ concentrations as great as 50 wt%. A 50 wt% uranium mononitridetungsten cermet was fabricated by impaction. The impacted density, 16.3 g/cm/sup 3/, was 99.0% of the theoretical density. Uranium monosulfide impacted to 99.0% TD showed improvements in physical properties over sintered US. A UO/sub 2/--50 wt % cermet was examined at temperatures to 1500 un. Concent 85% C by reflection electron microscopy. The effects of series of photomicrographs.
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: September 1963

Description: This report, from the Chemical Processing Department at HAPO for September 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.
Date: October 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION C, PROGRESS REPORT ON SEPARATIONS CHEMISTRY AND SEPARATIONS PROGRESS RESEARCH FOR JANUARY-JUNE 1963

Description: Cesium Recovery from Ores. Adaptation of the phenol extraction (Phenex) process to the recovery of cesium from ore leach liquors continued to show promise. In roast-leach tests, 98 to 99% of the cesium was dissolved from pollucite ore by roasting the ore at 800 deg C with 1.8 parts of Na/sub 2/CO/sub 3/ plus 1.2 parts of NaCl and leaching with water. More than 99% of the cesium was recovered from the leach liquor and separated from other alkali metals by extracting with 4-sec-butyl-2-( alpha -methylbenzyl)phenol (BAMBP) in diisopropylbenzene and stripping with hydrochloric acid. Santophen-1 also extracted cesium effectively, but, because of the limited solubility of the cesiumSantophen-1 complex in the diluent, the utility of this phenol in ore processing is questionable. Separation of Alkali Metals. The extraction and separation of alkali metals from nitrate solutions was studied with several different types of extractants, including substituted phenols, alkylphosphoric acids, sulfonic acids, carboxylic acids, and mixtures of some of these. With all of these reagents, cesium was extracted more strongly than rubidium, which in turn was extracted more strongly than the other alkali metals. Separation factors were higher with the phenols than with the other extractants. Acid Recovery by Amine Extraction. Preliminary tests showed the potential usefulness of tertiary amines for recovering and purifying phosphoric acid from the highly contaminated wet-process acid produced in the fertilizer industry. Water stripping of the amine solvent yielded a product that was more than 1.5 M in H/ sub 2/PO/sub 6/ and was almost free of iron and aluminum. Final-Cycle Plutonium Recovery by Amine Extraction. Batch equilibration tests with both aged and fresh samples of Purex-plant 1BP solution showed that the aged but not the fresh samples contained a considerable quantity of zirconium-niobium species highly extractable by the hydrocarbon diluents used with amines and other …
Date: October 25, 1963
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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