This report analyzes the President's authority to conduct war under the constitution, with and without Congressional approval. Contains a list of pros and cons of President Lyndon B. Johnson conducting war in Vietnam

At 100-H Area there are 13 locations and at 100-F Area 16 locations where radioactive material was deposited underground. Five of these locations, 2 at 100-H and 3 at 100-F, have been permanently terminated as burial sites in compliance with Radiation Control Standards. They contain solid waste with significant quantities of long-life radionuclides. Burial locations within the 105 Building exclusion fences were not marked with permanent posts as the exclusion fences are sufficient marking for such sites. Other locations not permanently marked were the components of the effluent systems, including the 107 retention basins, 1904 outfall structures and associated piping. Control objectives for these locations were to prevent contamination spreads and limit personnel access for several years. Similar objectives applied to locations where small quantities of liquid waste were released to ground, or small amounts of surface-contaminated materials were buried. At these locations, existing fences and radiation zone signs were left in place. The permanently posted burial grounds contain two general types of radioactive waste: neutron-activated reactor components, and surface-contaminated material and equipment. The activated components consist almost entirely of steel and aluminum. The most significant radionuclide contained in these materials is 5-year /sup 60/Co. The surface contaminants are primarily …

The calcined-waste containers produced during the Hot Cell Pilot Plant experiments in 1962 and 1963 have generated a maximum pressure of 3 psig. Design verification tests with the prototype spray calciner showed satisfactory performance when producing high melting point powders. Later tests on other feeds showed poor atomization and cake buildup in the calciner. Design of the prototype equipment is complete. Procurement and fabrication of prototype equipment is done except for a few cleanup items and final field-fitting of jumpers. Design verification tests on the pot storage station indicated satisfactory calorimeter performance. A GE-412 computer was successfully used in design verification tests for data collection, calculation, and correlations. Studies continued on fixation of sulfates from acid condensates generated in a glass-making process. Lead sulfate-borax melts produced by a continuous feed melter at 900/sup 0/C appear to be quite fluid, but exhibited a high (22%) evolution of sulfate. Studies were initiated on incorporation of the neutralized condensate into asphalt. Release rates of up to 2%/hr for /sup 137/Cs from a simulated phosphate ceramic waste material were observed from exposures to temperatures up to 1200/sup 0/C. Release rates of other isotopes which appear to be a thousand-fold lower than for cesium established …

It was the practice for several years to estimate the potential dose rate to the gastrointestinal from sanitary water sources by evaluating the results of radiochemical analysis of individual nuclides. The proposed method estimates the GI tract dose from Pasco and Richland domestic water from measurements of the total beta activity, and permits more frequent and more economical evaluation of a variable source of radiation exposure. Beginning with 1964 data, the GI tract dose rate for Richland and Pasco sanitary water has been obtained by multiplying the total beta count by a conversion factor derived from the historical relationship between the radiochemical analyses and the total beta counts. Either the accumulation of more data or changes in the relative abundance of the more significant nuclides in the water may result in changes in this factor.

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This monthly report details research and engineering operation activities of the Irradiation Processing Department for the month of September 1965.

This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.

The two small reactors (B and D) currently utilize a flat aluminum horizontal control rod consisting of three cooling tubes surrounded by boron carbide-aluminum neutron absorber rings and an outer casing of aluminum. Two adverse and complementary characteristics of these rods have served to limit the functional reliability of the rods under current and anticipated reactor operating conditions. The construction of the rod presents a relatively high resistance to transfer of heat from the sheath to the cooling water and the neutron to transfer of heat from the sheath to the cooling water and the neutron absorber rings show evidence of significant dimensional increase with high accumulated exposure to neutrons. With poor heat transfer and current reactor operating levels, the rod sheath temperature may exceed that for which aluminum is suited and the material loses its strength by annealing. Swelling of the neutron absorber rings further aggravates the overheating by increasing the cooling tube to ring gap. The net result is a tendency for hot spots to occur in the rod sheath and in the more advanced cases, these develop into e step plug. blisters which cause the rod to bind in the channel and/or the step plug. A new …

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This document examines potential yields from extended irradiation of plutonium in a Hanford K reactor. The study was made using the MOFOA program on the IBM-7090 Computer. Two types of plutonium were examined -- weapons grade plutonium and plutonium from (.22 w/o U- 235) depleted uranium irradiated to an exposure of about 2000 mwd/t. Both types of plutonium were irradiated for 3 years at an assumed 80 per cent operating efficiency.

Significant changes in fuel design, operating levels, loading geometry, and moderator condition have taken place since the Hanford reactors started operation. Changes which affect nuclear safety parameters require continuing analysis of the possible effects on safety system strengths and maximum potential reactivities. For this reason the shutdown of a Hanford reactor offered an excellent opportunity to measure many of the above factors without a significant production loss. Therefore a test program was proposed and carried out at H Reactor starting April 22, 1965 and ending May 5, 1965. All of the tests were designed to provide information concerning parameters which affect nuclear safety and control calculation limits. This document is a summary of the deactivation test results without application and recommendations to specific nuclear safety questions. Rather, it is intended that the results listed herein will serve as a basis for further study and application to nuclear safety technology.

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Declassified 28 Aug 1973. Several uranium oxide fuel materials were prepared for evaluation. Included was a 2-pound sample of plasma jet spheroidized. 30- to 60- mu UO/sub 2/ of precisely controlled stoichiometry containing less than 50 ppM metallic impurities. Six 1-pound samples of 30- to 60- mu U0/sub 2/ were prepared which contained calcium oxide, thorium oxide, or yttrium oxide stabilizing agents in solid solution. These powders were coated with 8 to 10 mu of tungsten by hydrogen reduction of tungsten hexaflouride in a fluidized bed. Seven 1-pound samples of 30- to 60- mu U0/sub 2/ containing various concentrations of yttrium oxide in solid solution were also prepared. Finally, a 1-pound sample of less than 5- mu UO/sub 2/ containing 10 mole% yttrium oxide was produced. Procedures were developed for applying metallurgically bonded tungsten coatings to the edges of W-U0/sub 2/ cermet fuel elements. These coatings were effective in reducing the U0/sub 2/ loss in high- temperature tests at NASA. Of several techniques examined for producing a halide- free tungsten coating on 30- to 60- mu U0/sub 2/ powder. the most promising were (a) vacuum evaporation of tungsten using electron beam heating, and (b) electrostatically bonding fine WO/sub 2/ powder …

A series of vibration tests were run at reactor temperature conditions to determine whether the control drum bearings could withstand wthe critical axial vibrations that might occur during ground tests of the NRX-A reactors. Additional tests will be required to evaluate the bearings under space operating conditions.

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