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5-gpm In-Pile Thorium Oxide Slurry Loop Development, Runs 14 Through 16 In Loop L-4-248, And Filtration Of Thorium Oxide Slurry With Sintered Filters

Description: In in-pile pump loop capable of circulating thorium oxide slurry while exposed to nuclear radiation in an experimental reactor beam hole is necessary to obtain information on the effect of reactor radiation on the physical and chemical properties of the slurry and on the corrosion-erosion of containment materials. Thorium oxide filtration test results with various sintered-metal filters and one aluminum oxide filter are reported.
Date: March 7, 1960
Creator: Baker, J. M.; Jones, D. T. & Savage, H. C.
Partner: UNT Libraries Government Documents Department
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20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962

Description: From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Date: March 1960
Creator: Vortman, Luke J. & MacDougall, H. R.
Partner: UNT Libraries Government Documents Department
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100-N Decontamination Facility Design Guide.

Description: Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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ABRAC---an IBM-704 Three Dimensional Nuclear-Thermal Depletion Program With Distributed Void Effects

Description: ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date: March 1960
Creator: Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT

Description: An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mil… more
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
open access

Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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Apparent Copper Rate Constants Determined In In-Pile Loop Experiment L-2-22

Description: The results of radiolytic gas pressure measurements in the pressurizer of in-pile loop experiment L-2-22 were used to calculate the copper rate constants in the several different test solutions. Values for the copper concentration obtained from solution analyses were combined with the solution rate constants to determine the apparent molar rate constant for each solution at 280'C.
Date: March 23, 1960
Creator: Jenks, G. H. (Glenn Herbert), 1916- & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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The Applicability of Packed Glass Raschig Rings For Nuclear Safety In Large Vessels

Description: Simple calculations indicate that large diameter vessels packed with boron-containing glass raschig rings are applicable for storage of high concentration solutions of fissile material. Use of this means for storage of fissile solutions can result in appreciable savings. Advantages and disadvantages are discussed and tests are enumerated that must be made to confirm the applicability of glass raschig rings as a fixed poison.
Date: March 24, 1960
Creator: Nichols, J. P.
Partner: UNT Libraries Government Documents Department
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The Application of Nuclear Energy to Agriculture

Description: Differences were found in the radiosensitivity of cacao clones. Studies are continuing to see if these differences are related to nuclear damage. Radiosensitivity of rubber, palms, and bananas are being studies. Angustifolia mutants appeared from irradiated coffee seeds. The response was linear with thermal neutrons but exponential with gamma rays. The hypothesis of a two hit chromosomal aberration is being tested with coffee and Crotalaria which probably gave an exponential response (sectorial… more
Date: March 1, 1960
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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Applications of Magnesium Diffusion To The Reprocessing Of Zirconium-Clad Fuel Elements

Description: Magnesium diffusion into zirconium and Zircaloy-2 was studied to determine whether the resulting alloys were amenable to reprocessing. The effects of magnesium grain-boundary diffusion on zirconium and Zircaloy-2 were studied by corrosion and mechanical deformation tests.
Date: March 4, 1960
Creator: Federer, J. I.
Partner: UNT Libraries Government Documents Department
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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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Automatic alum feed device to produce water of any given clarity

Description: This report documents the research and testing of an automatic alum feed process at the Hanford reservation. This process generates water of varying qualities which is used to cool fuel elements in nuclear reactors.
Date: March 7, 1960
Creator: Conley, W. R. & Pitman, R. W.
Partner: UNT Libraries Government Documents Department
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Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department
open access

The Blast Cleaning Process as an Aid to Visual Weld Inspection

Description: Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.
Date: March 9, 1960
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in len… more
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department
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Burst testing of irradiated Zircaloy tubing. Revision 1

Description: An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diam… more
Date: March 4, 1960
Creator: Kahle, V. E.
Partner: UNT Libraries Government Documents Department
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Cathode brazing control for GEXF

Description: As a result of repeated epidemic losses of brazed cathodes at GEXF, the engineering work necessary to determine the best brazing cycle and the controls necessary to insure reproducibility and high yields in the future was carried out by means of EN-297. Included are the procedures used and the tests made to verify the conclusions drawn and the recommendations made.
Date: March 8, 1960
Creator: Thinnes, E.L.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for February 1960

Description: Production Pu nitrate and unfabricated Pu metal during Feb. was below forecast; however FY output is above forecast. Production of UO{sub 3} exceeded commitments; shipments met schedule. Decontamination performance of Purex solvent extraction system was subnormal. Pu nitrate solutions were concentrated. A fire occurred in Purex N Cell during conversion of ion exchange prototype to production facility.
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section B Monthly Progress Report, March 1960

Description: Consolidated Edison type fuel pellets were irradiated and analyzed, to determine the extent of fracturing, particle size of fines produced, and the rate of dissolution in boiling 13M HNO/sub 3/-0.04M NaF -0.1M Al(NO/sub 3/)3. Fused sodium or potassium hydroxide was used to shatter the pellets at 400 deg C or higher. Similar pellets were dissolved in H/sub 3/PO/sub 4/ and fused ammonium bifluoride. An investigation was made of the thermodynamics and limits of flammability of gases expected durin… more
Date: March 1, 1960
Creator: Blanco, R E
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for December 1959 and January 1960

Description: The recovery of Th from Blind River ion exchange barrens with di(2- ethylhexyl)phosphoric acid was investigated. The recovery of Tc and Np from fluorination plant residues with tertiary amine was studied. The extraction of Np/sup 4+/ by quaternary ammonium nitrates is reported. A solvent recovery procedure involving successive use of Na/sub 2/CO/sub 3/washing and Al/sub 2/O/ sub 3/- adsorption was demonstrated in laboratory tests as a possible method for the purification and decontamaination of… more
Date: March 1, 1960
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Gresky, A. T. et al.
Partner: UNT Libraries Government Documents Department
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A COLORIMETER FOR IN-LINE ANALYSIS OF URANIUM AND PLUTONIUM SOLUTIONS

Description: A colorimeter is described that can be used to monitor process solutions continuously for uranyl nitrate or plutonium nitrate concentration. The instrument was tested under plant conditions in the concentration range from 0.1 to 70 grams of uranium per liter and 0.1 to 10 grams of plutonium per liter. The instrument error was plus or minus 1% of the span, but errors of 15 to 20% can be caused by other variables such as acidity and other salts present. (auth)
Date: March 1, 1960
Creator: Colvin, D. W.
Partner: UNT Libraries Government Documents Department
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