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A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)

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.

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 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.

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 …

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" A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to which the encapsulated gases and particles can diffuse and be removed."

The cobalt and molybdenum positions had been derived from a three-dimensional Patterson function based on complete data out to λ-1 sin θMo≈ 1. From the separation of the separation of the Mo atoms it was thought that the structure contained free, unlinked MoO4 -2 ions, and this, together with the observed density and analyses for Co and Mo, suggested that the composition was probably Co2(MoO4)3. The paucity of structural information on complex oxide systems and the interesting properties, both structural and physical, of such systems prompted the present, detailed refinement of the structure. The result is more complicated and more interesting than had been anticipated: from the analysis of the X-ray data the compound is found to be NaCo2.31(MoO4)3, and this composition is consistent with chemical analyses. The structure shows several interesting features, including the partial occupancy of cobalt atoms in two independent CoO6 octahedral sites. In one arrangement of CoO6 octahedra there is the not too common face sharing to form infinite columns; in the other arrangement a zig-zag sheet, as far as we know differing from anything thus far reported, is formed by the sharing of edges and corners.

The analysis of closed circuit systems in which spontaneous steady-state electric currents appear can be carried out with the use of the function [function not transcribed]. The analysis indicates that any open circuit system of the form. Phase 1, barrier 1, phase 2, ......, phase b, barrier b, phase 1' is a chemical source of electromotive force when the phase 1 and 1' are identical, when the system contains two or more barriers whose sets of ionic transport members are different, and when the system is composed of two or more phases whose chemical properties are different. A general expression for the electromotive force of model systems composed of homogeneous phases and biological membranes in linear array can be written as [expression not transcribed] in which the indicated summations are to be performed for all barriers and for all ions to which each barrier is permeable.

A kinetic study of the exchange of normal and radioactive bromine in graphite-bromine lamellar compounds has been made at temperatures of 30° to 50°C. Natural and synthetic graphite powders were investigated. Two alternative mechanisms for the exchange, volume diffusion and surface exchange, were considered. The data were in better agreement with the diffusion mechanism. Diffusion coefficients of 10 -9 to 10 -8 cm2/sec and an activation energy of 11 to 14 kcal/mole were calculated for the natural graphite powders. The diffusion coefficients increased with increasing bromine content. Reversibly absorbed bromine exchanged more rapidly than irreversibly absorbed bromine.

The role of the marrow as a site for antibody formation has been considered for many years. In 1912 Ludke reported the appearance of antibody in cultures of marrow cells obtained from previously immunized rabbits. Specific agglutinins for killed typhoid bacilli and lysins for ox red cells and sheep red cells were detected in the culture media 2 to 5 days later. However, the cultured cells failed to produce antibody when these antigens were added to the media. Similar findings by Reiter, Przygode, and Schilf appeared in the early literature with regard to the appearance of antibodies to various antigens in tissue cultures of bone marrow from immunized animals, along with failure to elicit antibody formation by addition of antigen to the culture resulted from the addition of excess amounts of antigen, so that if antibody synthesis occurred, the excess antigen combined with antibody and significant amounts of free antibody could not be detected in the culture media. Thorbecke and Keuning observed an increase in antibody in culture fluids when bone marrow fragments from rabbits immunized to paratyphoid B vaccine were cultured in roller tubes.

Cowley's measurements of the short-range order parameters, αi, in Cu3Au at T=405°C have been re-evaluated taking into account the effects of thermal vibrations and static displacements due to differing atomic sizes. The separate corrections for the thermal vibrations and the first-neighbor atomic size factor are found to be quite large, demonstrating their importance in the usual experiments. When combined, the corrections in this case largely cancel, and only the values of α1 and α3 are appreciably changed. The corrected values are: α1= -.113, α2= +.185, α3= -.009, α4= +.082, α5= -.058.

An isochronal differential-type microcalorimeter has been designed and constructed. As a result of its simple design it is very easy to handle the samples and assemble the calorimeter. Important to the operation of the calorimeter is a program, also working on the differential principle, that provides linear temperature rise of the samples. This calorimeter is used to measure very small energy releases such as those found in precipitation, stored energy, etc. It is demonstrated that the calorimeter is easily capable of measuring 0.0005 cal with a probable error of the order of 1% to 2%.

The enzymolysis by α-chymotrypsin of the substrates, N-acetyl-L-tryptophane ethyl ester and N-acetyl-L-tyrosine ethyl ester, was followed by means of fluorescence whose intensity increased fourfold and threefold per mole respectively as substrate was transformed into amino acid. The assay by fluorescence was several orders of magnitude more sensitive than the assay by differential absorption spectra of these substances and was in agreement with it in those concentration regions where both methods overlap. To maintain linearity between concentration and fluorescence intensity, the concentration of substrate should be no greater than 10-4 M/1. In such solutions the rate of esterolysis could be followed with the enzyme at 10-11 M/1.

The purpose of this paper is to present tables of the perturbed wave functions which have been recently obtained in a calculation of the quadruple antishielding factors γ∞ for the Mn+2, Fe+3, Ga+3, and Ag+ ions. The wave functions v'1(nℓ-ℓ) which are tabulated represent the effect of the perturbation due to a nuclear quadruple moment Q on the wave functions of the outermost electrons of the ion core.

Innes, Zemen, Frenkel, Borner and Wright (1962) described an outbreak of encephalitozoönosis of the central nervous system in mice, a summary of which is given below for an understanding of why this appendix may be of interest. When the paper was presented for publication, the editors of the journal decided to omit the history of our mouse colony. In our opinion, to understand (a) how this infection may have arisen and (b) may have spread, and still exist in some colonies, it is of prime importance to know the history of this strain of mice used by us (and others). It also has lessons on the establishment and maintenance of so-called "disease-free" or "specific pathogen-free"* colonies of laboratory animals in general. Information on the history of the mice has been culled from Col. H. Yager, VC, Director of the Division of Veterinary Medicine, Walter Reed Army Institute of Medical Research, Washington, D. C., and from Drs, Clara Lynch and John B. Nelson, Rockefeller Institute, New York.