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Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

Description: The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
Partner: UNT Libraries Government Documents Department
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PHOTOSENSITIZED IONIZATION OF ALKALI METAL VAPORS

Description: The vapors of potassium, rubidium, and cesium have been photoionized with light absorbed in the discrete region of the atomic spectrum. The energy threshold for the ionization process has been determined and the ions produced identified by mobility measurements. The data give lower limits for the dissociation energies of K{sup +2}, Rb{sup +2} and Cs{sup +2}. Each of these molecular ions has a bond energy approximately 50% greater than that of the corresponding neutral molecule. In addition, lower limits for the electron affinities of the alkali atoms and approximate values for the mobilities of Rb{sup +} and Rb{sup +2} in rubidium vapor are given.
Date: February 1, 1965
Creator: Lee, Yuan-tseh & Mahan, Bruce H.
Partner: UNT Libraries Government Documents Department
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Computer calculation of angular momentum coupling coefficients and of (d,p) stripping reaction cross section. Technical report No. 14. [B53 DWC, B53GOR, B53RIM, B53SIX, in FORTRAN]

Description: A theoretical expression for the stripping differential cross section is derived and prepared for computer evaluation. Input information is provided for the code B53DWC, which calculates this cross section, and the codes B53GOR, B53SIX, and B53RIM, which evaluate 3-J, 6-J, and 9-J coefficients. (RWR)
Date: February 1, 1965
Creator: Strobel, G.L.
Partner: UNT Libraries Government Documents Department
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Production Test IP-719: The effect of water plant variables on effluent activity. Final report

Description: One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter run, a half-plant test was initiated at DR Reactor on September 28, 1964, under the authorization of Production Test IP-719. This report presents the results of the test. The water treatment plant at DR Reactor was operated for a three-month period with half the filters on a seven-hour filter cycle and the other half on a 5.25 hour filter cycle. The shorter filter cycle did not significantly reduce either the filtered water turbidity or the P{sup 32} and As{sup 76} concentration in the reactor effluent. It can be concluded that in the range investigated effluent activity is not influenced by the length of filter cycle as long as breakthrough is avoided.
Date: February 23, 1965
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Examination of furnace belt failure in 232-Z incinerator

Description: Metallographic examination has been completed on samples from the Nichrome V wire mesh furnace belt in the 232-Z building incinerator. During service the furnace belt had broken in several places where the wire was welded together. A grain boundary phase was found in weld metal during metallographic examination of the as received material. It is probable to conclude that the failure during service was caused by accelerated corrosion of the weld and that the accelerated corrosion in that area was related to the structure of the weld metal. It would be informative to examine welds from the furnace belts that have not failed to further study the cause for the failure.
Date: February 11, 1965
Creator: Nelson, T. C.
Partner: UNT Libraries Government Documents Department
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Technical feasibility of using uranium oxide fuels at Hanford

Description: The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated values. The research and development program is estimated to require $3.6 million over a three-year period. Technical aspects of using oxide are discussed in general for N, K, and the smaller reactors. The variations in uranium-to-graphite weight ratio and operating conditions vary the limitations encountered with each reactor type with an oxide fuel cycle. Plutonium separation and uranium oxide recycle on site have been examined, and a technical review of the limitations and the additional process requirements are presented.
Date: February 15, 1965
Partner: UNT Libraries Government Documents Department
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Pressure drop characteristics of solid aluminum dummy patterns in K Zircaloy-2 process tube

Description: Pressure drop tests were performed in the 189-D-Hydraulics Laboratory to determine the number of K-Reactor solid aluminum pieces (SAs) required to throttle the tube flow of a 46-piece KVE and a 38-piece KVN arch-rail I&E fuel charge to that of a corresponding bridge-rail charge. In addition, the effects on Panellit pressure and tube flow were determined for several cases.
Date: February 16, 1965
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
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Research and Engineering Operation Irradiation Processing Department monthly record report, January 1965

Description: Process and Reactor Development progress includes depleted uranium irradiation in the B and KE reactors and thoria irradiation in the B, C, D, KE, and KW reactors. Reactor Engineering reports on higher graphite temperature tests, graphite strength tests, heat removal requirements following reactor shutdown, and reactor deactivation. Reactor Physics topics include: E-Q loading, test facility loss of coolant protection, ball 3X replacement, and in-core flux monitors. Radiological Engineering reports on radiation control experience, classification, radiation occurrences, effluent activity data, radiation standards and controls and procedures, and dose rates in the DR reactor block. Also listed are many revised standards issued during the report period. Operational Physics Operations report on pile physics plant assistance for the B, C, D, DR, F, H, KE, AND KW reactors. Process Physics studies include reactivity and control studies and product related studies.
Date: February 3, 1965
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Evaluated Neutron Cross Sections for Tritium

Description: From foreword: Evaluation of the experimental data on the light isotopes, hydrogen through beryllium, was initiated by LASL in mid-1963. Since the data compilations available were completely inadequate for the task at hand, the tedious program of compiling and plotting was undertaken. As the work progressed an attempt was made to eliminate many of the obvious errors and inconsistencies found in the literature and existing compilations.
Date: February 1965
Creator: Stewart, Leona
Partner: UNT Libraries Government Documents Department
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Photoelastic evaluation of Phoebus 2 main closure design

Description: A two dimensional photoelastic study of two designs of clamps for the Phoebus 2 main closure is detailed. Predicted prototype stress data is given in the form of a stress parameter which includes the axial load and a representative clamp radius.
Date: February 5, 1965
Creator: Fischer, M. A.
Partner: UNT Libraries Government Documents Department
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Experience in the Shipment of Yankee Fuel Assemblies for Post-Irradiation Examination

Description: From abstract: This report presents the knowledge and experience gained from fifteen spent Yankee Core I fuel assemblies shipments. It discusses the equipment employed, the approvals required, and the technical and administrative problems that had to be resolved.
Date: February 1965
Creator: James, B.; Payne, D. D. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department
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Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)

Description: A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward optimizing deposition process parameters to attain control of qualities such as coating thickness, uniformity, density, impurity content, and surface quality. Substrate penetration methods have been investigated in the interest of completely eliminating the interface between the fueled substrate and cladding. In addition, the effects of process parameters and post-cladding heat treatments on the fuel retention properties of clad composites at 4500 degrees F (2480 degrees C) in hydrogen for 2 hours have been evaluated. As a result of work performed during the first phase of the program it has been shown that the rate of deposition of tungsten from WF 6 and the uniformity of the deposit can be varied in a predictable and reproducible manner by exercising control over the temperature, pressure, and gas flow rates at which the deposits are produced. A significant result of the study is the discovery that substrate nucleation and epitaxial growth in deposits made on both unfueled tungsten and fueled substrates may be effected by pretreating the substrates in hydrogen. High temperature fuel retention testing of tungsten clad W-U02 at 45000F (2480 degrees C) in hydrogen for 2 hours has demonstrated that the vapor deposited layer effectively and consistently restricts fuel loss.
Date: February 15, 1965
Creator: Lamartine, J.T. & Hoppe, A.W.
Partner: UNT Libraries Government Documents Department
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A Small-scale Investigation of the Possibility of Constructing Low-Relief Earth-Fill Dams Using Nuclear Explosives

Description: The experiment described herein has shown that the concept of low dams produced by ballistic collision of ejecta from simultaneous detonation of properly spaced parallel rows of charges is a feasible one. Rows of 8-pound charges were buried 3 feet deep with 4-foot spacing between charges. When two such rows of charges were placed parallel and 17.5 feet apart, the maximum height of the "dam" was achieved. The spacing of 17.5 feet between rows corresponds to 4.7 times the crater radius of one 8-pound charge at the burial depth which maximizes the single-charge crater. The extrapolation of these results to larger explosions is discussed. The height decreases and the width increases as the spacing between rows is further increased. The mass of material in the "dam" cannot exceed that in the crater of one of the rows. At the spacing between rows which maximizes height, the volume of the "dam'' is about 50 percent of maximum volume theoretically achievable. At wider spacings, the volume increases to 75 percent.
Date: February 1965
Creator: Vortman, Luke J.
Partner: UNT Libraries Government Documents Department
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