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Air-Core Strong Focusing Synchrotron

Description: The following report is based on work performed under the auspices of the U.S. Atomic Energy Commission. The purpose of this report is to describe an air-core strong focusing synchrotron and its functions.
Date: August 21, 1959
Creator: Christofilos, Nicholas C.
Item Type: Refine your search to only Report
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An Analytical Evaluation of the Effects of an Aerodynamic Modification and of Stability Augmenters on the Pitch Behavior and Probable Pilot Opinion of Two Current Fighter Airplanes

Description: Memorandum presenting the effects of wing modification and stability augmentation on the computed longitudinal behavior in the pitch-up region and probable pilot opinion of the pitch-up characteristics of two current fighter airplanes. An exploration of the addition of a wing-leading edge is included. Results regarding computed pitch-up behavior and probable pilot opinion are provided.
Date: April 21, 1959
Creator: Sadoff, Melvin & Stewart, John D.
Item Type: Refine your search to only Report
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Item Type: Refine your search to only Report
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Braze Alloys v.s. Atmospheres : Final Report Project 1325

Description: Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, suffici… more
Date: May 21, 1959
Creator: Rogers, S. L.
Item Type: Refine your search to only Report
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CARBOXYLATIONS AND DECARBOXYLATIONS

Description: A brief survey of decarboxylation reactions and carboxylation reactions that are known or presumed in biological systems will be presented. While a considerable number of amino acid decarboxylations are known, their mechanisms will not be included in the present discussion but will be reserved for a later paper in the symposium. The remaining decarboxylation reactions may be subdivided into oxidative and nonoxidative decarboxylations. In most cases, these reactions are practically irreversible … more
Date: April 21, 1959
Creator: Calvin, Melvin & Pon, Ning G.
Item Type: Refine your search to only Report
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Chemical Processing Department Monthly Report: December 1958

Description: This report for December 1958, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date: January 21, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
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Chemical Processing Department Monthly Report: August 1959

Description: This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: September 21, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
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Chemical Processing Department monthly report, April 1959

Description: Production of Pu from separations plants was only 58% of April commitment because of Purex difficulties. UO{sub 3} production, shipments met schedules. Pu shape production and shipments exceeded forecast by 14%. Purex HS column, repaired Oct 1958, developed another leak and was bypassed April 18, resulting in Pu and U that required reprocessing. A Palm recovery run at Purex with all- reducing flowsheet, resulted in 87% recovery and excellent decontamination of product. The prototype dual-pass s… more
Date: May 21, 1959
Item Type: Refine your search to only Report
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Chemical Processing Department monthly report, July 1959

Description: Pu production from separation plants was only 65% of the monthly commitment owing to Purex difficulties. UO{sub 3} production and shipments both met schedules. Although unfabricated Pu metal production was reduced, all shipping commitments were met on schedule. Purex equipment responded satisfactorily to decontamination. 860,000 Ci of Ce{sup 144} were recovered from Purex Conc. IWW. The all-Ti L-3 concentrator loop was installed in the Redox Pu Concentrator. The safety of the slag and crucible … more
Date: August 21, 1959
Item Type: Refine your search to only Report
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Chemical Processing Department monthly report, May 1959

Description: Pu production from separation plants during May was 116% commitments. UO{sub 3} production and shipments met schedules. Button output and shape production was 97 and 121% of schedule/forecast. Recuplex (product recovery) operated at record rates. Processing at Purex was carried out with the HS column bypassed. Palm processing resulted in excellent product quality but with low yield. A sample of fission products was prepared for Curtiss-Wright. Piping modifications were made to the Purex Pu ion … more
Date: June 21, 1959
Item Type: Refine your search to only Report
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Chemical Processing Department monthly report, November 1959

Description: The November 1959 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: December 21, 1959
Item Type: Refine your search to only Report
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for April 1959

Description: A concentration cell electrode was installed in a fritted glass surface and was used to measure the surface KCl concentration while water was being transpired through the surface into a mixed tank of 0.1 M KCl. The results from the first Fluorox run made with crude UF/sub 4/ showed that 85.3% of the theoretical amount of UF/sub 6/ was accounted for, with 17.9% being collected in cold traps and the remainder being consumed in various side reactions. Installation was completed of apparatus to stu… more
Date: July 21, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
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Comparative Costs Of Sea Disposal And Land Burial For The Radioactive Wastes Of The Lawrence Radiation Laboratory

Description: This report is a comparative cost study of radioactive waste disposal for the Lawrence Radiation Laboratory (UCRL). In particular, it compares the costs of sea disposal in depths of 1000 fathoms and of 2000 fathoms off the California coast with land burial of the wastes at the Hanford Atomic Products Operation (HAPO), Richland, Washington, at the National Reactor Testing Station (NRTS), Idaho Falls, Idaho, or at the Nevada Test Site (NTS), Nevada. In the comparison, the cost of utilizing a comm… more
Date: January 21, 1959
Creator: Nielsen, Elmer
Item Type: Refine your search to only Report
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Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

Description: Property changes to common graphites resulting from reactor irradiation depends strongly on the temperature of exposure. Radiation affects at 30 C and 400 to 500 C are quite well known; however, at intermediate temperatures, results are not well known although a large volume of graphite in most reactors operate in this range. Production test, IP-22A, was reactivated, after a dormant period of many months, to study radiation damage between 30 and 400 C. This report concerns mainly the experiment… more
Date: October 21, 1959
Creator: Koyame, K.
Item Type: Refine your search to only Report
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Design of Production Test IP-247-A-8-FP, irradiation of 1.47% enriched self-supported I&E fuel element in ribless process tubes. Revision

Description: To evaluate the self-supported fuel element concept, tests are underway to determine the performance of collapsible bridge-rail supported fuel elements in ribless process tubes under present reactor conditions at B Reactor. It appears expedient, however, to extend this evaluation to future operating conditions in order to establish the relative feasibility of conversion to self-supported fuel elements in ribless tubes in present reactors. Utilization of 1.47% U-235 enrichment will provide fuel … more
Date: August 21, 1959
Creator: Hodgson, W. H. & Hall, R. E.
Item Type: Refine your search to only Report
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Direct Spectrophotometric Determination of Uranium in Cyclohexane Solutions of Tri-n-Octylphosphine Oxide

Description: A method for the direct determination of uranium in a cyclohexane solution of tri-n-octylphosphine oxide (TOPO) is presented. The adduct, UO/sub 2/ Cl/sub 2/ x 2TOPO, that is formed when uranium(VI) is extracted from hydrochloric acid solutions by tri-n-octylphosphine oxide absorbs light in the ultraviolet region. This absorbance is measured at 230 m mu vs. a TOPO-cyclohexane solution that was contacted with hydrochloric acid of the same concentration as that in the test aliquot. The molar abso… more
Date: April 21, 1959
Creator: White, J. C.
Item Type: Refine your search to only Report
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DOSE AND FLUX MEASUREMENTS ON GODIVA RADIATION EFFECTS EXPERIMENTS

Description: Flux and dose measurements of fast neutrons, thermal neutrons and gamma rays under perturbing conditions using Godiva as a source are described and discussed. The limitations of single monitoring devices are noted. It is pointed out that in order to improve the accuracy of flux and dose measurements in radiation effects studies, specific detectors must be used at the position of the experimental object. (auth)
Date: September 21, 1959
Creator: Harris, P.S.; Montoya, E.F. & Schweitzer, W.H.
Item Type: Refine your search to only Report
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EFFECTS OF IRRADIATION ON STAINLESS STEEL-CLAD UO$sup 2$ PELLETS IN HELIUM OR CARBON DIOXIDE

Description: Uranium dioxide pellets sealed in Type 316 stainless steel containers with a helium gas were irradiated in helium and in C0/sub 2/ in thermal fluxes or the order of 1 x 10/sup 13/ n/(cm/sup 2/)(sec). Cladding-surface temperatures were reportedly between 1200 and about 1800 F. The hot-cell examination performed by BMI showed that there were no obvious effects of the irradiation on the specimen tested in helium. However, the specimen irradiated in the presence of C0/sub 2/ exhibited severe claddi… more
Date: April 21, 1959
Creator: Lamale, G.E.; Gates, J.E. & Dickerson, R.F.
Item Type: Refine your search to only Report
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EXPERIMENTAL AND ANALYTICAL STUDIES OF REFLECTRO CONTROL FOR THE ADVANCED ENGINEERING TEST REACTOR. PART A. EXPERIMENTAL STUDIES WITH THE REFLECTOR CONTROL SYSTEM MODEL. PART B. ANALYTICAL STUDIES OF REFLECTOR CONTROL

Description: Studies of reflector control for the Advanced Engineering Test Reactor were made. The performance of various parts of the reflector control system model such as the safety reflector and the water jet educator, boric acid injection, and demineralizer systems is discussed. The experimental methods and results obtained are discussed. Four reflector control schemes were studied. The schemes were a single-region and three-region reflector schemes two separate reflectors, and two connected reflectors… more
Date: October 21, 1959
Creator: Bertelson, P.C. & Francis, T.L.
Item Type: Refine your search to only Report
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Final report on the fuel and target element evaluation at increased irradiation levels for tritium production: Production tests 313-105-35-M and 105-562-A

Description: The C Reactor was proposed for producing tritium. To evaluate the performance of enriched U-Al J elements and natural Li-Al alloy target (N) elements, 60 charges containing both J and N pieces were irradiated under a variety of conditions in C Reactor. No ruptures were sustained; however Tube 3276-C was discharged because of a suspect. Corrosion rates of J elements were not worse than for natural U irradiated under same conditions. Differences between corrosion of J elements prepared by three d… more
Date: December 21, 1959
Creator: Hodgson, W. H.
Item Type: Refine your search to only Report
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