Station 1A was the emplacement hole for the nuclear device used in the Advanced Research Project Agency's and U.S. Atomic Energy Commission's 5-kT nuclear Salmon Event of October 22, 1964. The hole penetrated the Pascagoula and Hattiesburg Formations, undifferentiated, and the Catahoula Sandstone, all of Miocene age, before entering the caprock at a depth of 882 feet. In continued through the calcite, gypsum, and anhydrite units of the caprock, which extend to a depth of 1,469.5 feet, and terminated in the salt stock at a depth of 2,802 feet. Five sand aquifer units lie above the caprock, whereas one sand aquifier lies within the calcite unit of the caprock. Drilling activities did not cause noticeable water-level fluctuations in the sand aquifers; however, during drilling in the calcite caprock, drilling fluid losses twice caused significant but temporary rises in water level in three observation wells that monitor the calcite limestone aquifer. The microscopic examination of drill cuttings collected at 10-foot intervals to a depth of 1,220 feet in Station 1A is presented. 2 figures, 1 table.

This report gives the exposure data for the C Reactor at the Hanford Reservation February 1965.

During the 18-year history of Hanford operations, a high degree of safety has been provided at reasonable cost by the storage of high-activity liquid wastes in underground tanks, by the percolation of low-activity liquid wastes (principally water) through the soil to the ground water, and by the adsorption or filtration of radioactive materials from gaseous effluents prior to their discharge to the atmosphere. Studies of the Hanford area indicate that current practices could be continued almost indefinitely without jeopardizing environmental safety, provided the stored liquid wastes are periodically transferred to new tanks before the existing ones fail. In 1960, a Fission Product Recovery Program was prepared outlining a plan to meet the Atomic Energy Commission`s needs for isolated fission products. Emphasis was placed on developing processes for isolating selected fission products and on providing interim production capability for recovering the fission products of immediate interest. In 1961, development efforts were channeled almost exclusively toward meeting the immediate needs of the Commission for separated strontium-90 and cesium-137. During this time, it became increasingly evident that substantial economies could be realized, both in immediate development and subsequent operating efforts, if the separate fission product recovery and waste management programs were merged. The …

It is recommended that the ``square pile`` concept be adopted for all disaster total control calculations, and that the basic reactor constants listed in HW-62884, except for Ball 3X local strength at the DR Reactor, be used in applying this method. Curves are included for each reactor type, indicating allowable enrichment based on appropriate local control strengths. (The reactors whose operating methods are affected by disaster total control requirements are B, D, F, and DR Reactors; the remaining piles have sufficient geometrical coverage). An example of the analytical method is included.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Suspension of driver’s license of defendants after being convicted of the misdemeanor offense of DWI or the felony offense of DWI second offense and being placed on probation.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Whether a constable may act as a deputy tax assessor-collector for one day in a poll tax drive put on by the Jaycees.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Crawford Martin, regarding a legal question submitted for clarification: Territorial limits of the Burnet Independent School District.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Crawford Martin, regarding a legal question submitted for clarification; Effect of H.B. No. 170, (vesting Texas Water Development Board with eminent domain powers), on existing water authorities or districts.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Effects of proposed Senate Amendment to H.B. 122, the House Salary Suspension Act.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Construction of proposed rider to the General Appropriations Bill.

The purpose of this study is to provide budgetary data for modifying and monitoring the present water treatment process at B, C, D, KE, and KW reactor plants to effect a reduction in the activity of the reactor effluent water discharged to the Columbia River. The study is subdivided into three parts: facilities for sodium silicate addition at each reactor water plant, on-plant facilities for the manufacture and supply of sodium silicate, and instrumentation for monitoring the water treatment process for standardizing water quality in the water treatment plants. While the present concentrations of radionuclides discharged to the river are well below the maximum permissible concentrations established by the National Bureau of Standards, the proposed reduction is in the interest of providing greater protection from potential radiation exposure to people living downstream from the Hanford Plant where economically practicable.

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On February 13, D Reactor sustained a bumpered enriched fuel element failure in process tube 3289. The element failed in the twenty-first position from the rear of the charge and was from lot KY-928-Q. Visual examination of the failed element indicated the failure mechanism to be cleavage of the uranium core. This conclusion was substantiated in part by the appearance of ``worm tracks`` in the aluminum jacket. The fuel failure was detected approximately three hours after the reactor had resumed operation from a minimum outage. Examination of reactor operation during the three-hour period revealed no evidence of a power transient which might account for the failure mechanism. As a result of a previous meeting between the management of Process Technology Subsection and Production Fuels subsection, verbal information was received from PFS which possibly explains the failure mechanism experienced with this lot. An agreement reached in the meeting was that PFS would provide Process Analysis with fuel lot canning history for evaluating continued irradiation of fuel failure lots with questionable quality integrity.

Steady state hydraulic demand curves were obtained for tube powers of 500, 1000, 1500 and 2000 KW with an inlet water temperature of 20C and a rear header pressure of 25 psig. These curves are shown in figures. The point of initial unstable flow for various tube powers is shown for a front header pressure of 325 psig. The flow rate that would lead to the initial point of unstable flow as a result of a sudden plug upstream of the Panellit tap is shown in a figure.

The feasibility of fabricating aluminum clad, low-density ({approximately} 65 per cent theoretical density) thoria elements using thoria produced-by a modified Sol Gel process, low frequency-low energy vibration for compaction, and the TIG welding process for closure welding has been demonstrated by Hanford Laboratories (HL). They have also assembled thoria fuel elements for the initial irradiation to produce 1 to 2 kgs. of U-233. At this time, it is expected that Hanford will be asked to produce about 25 kg. of ``clean`` U-233 and that authorization to proceed with this program could be expected sometime between now and late fall of CY 1964. The requirements in terms of equipment and manpower, and the time schedules to produce this quantity of U-233 have been published and it was indicated, based on best estimates made at the time, that finished thoria fuel elements could be produced 7 months after authorization of the program, and the full 60 tons of fuel elements completed 9 months after authorization. Approximately $125,000--150.000 of capital equipment in Production Fuels were estimated as being required to produce the quantity of fuel elements required, including prototypes used in engineering development. This report reassesses the Production Fuels Section capability to meet …

The design, performance, and cost information on the nuclear portion of the Mixed Spectrum Superheater power plant are emphasized. The research and development programs required to ensure plant feasibility are also presented. The nuclear steam supply system, reactor auxiliary systems, radiation control systems, control and instrumentation, special test instrumentation, plant operation and maintenance, steam cycle, turbine plant, general service systems, preliminary safeguards considerations, expansion of plant power output to 150 Mw(e), and MSSR critical experiment are described. (M.C.G.)

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A system of six codes is described that permits the solution of a broad class of problems encountered in the study of neutron thermalization, average cross sections, and spectral models. These programs are all compatible with use on MONITOR for the IBM 7090. The Fortran listings are given. (auth)

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A transfer function for d-c operational amplifiers with generalized input and feed-back networks is derived by application of network theory. This transfer function, more general than others in common use, applies to three and four-terminal networks. It contains, as a special case, the well-known transfer function for d-c operational amplifiers with two-terminal networks. Examples are given. (auth)

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