The purpose of this report is to provide a brief written description of the facilities existing at Hanford for research and development in the fields of heat transfer and hydraulics.

C Reactor experienced two severe fuel failures, one in process tube 2562 on 10-27-67, and one in process tube 3361 on 12-27-67, both resulting in major efforts to effect their removal. The intent of this document is to present a summary of the action taken for the removal of the failed elements.

The total cross sections for resonant charge exchange have been measured as a function of energy in the range from 10 to 500 eV for the Cs{sup +}-Cs, Rb{sup +}-Rb, and K{sup +}-K systems. The agreement with certain data obtained at higher energies for these systems, and with theoretical cross sections of Smirnov is satisfactory.

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The purpose of this report is to explain the computerized method of reporting operating quality costs at the Neutron Devices Department (NDD), St. Petersburg, Florida. Quality Control Management recognized the need to report operating quality costs more meaningfully. With the aid and cooperation of the Finance Section, a GE 415 computerized (COBOL) procedure was developed and implemented at NDD to measure quality cost expenditures more effectively. The detailed procedure and explanation of pertinent quality cost activities can be found in the Appendices.

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of March 1968.

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A method utilizing a diffusion controlled electrochemical reaction was used to measure average and instantaneous mass transfer coefficients at the solid-liquid interface in upward gas-liquid climbing film flow in a vertical annular duct. These measurements give some indication of the mechanics of flow of the film, the extent of turbulence at the inner wall, and the effect of film thickness and wave motion on the mass transfer process at the inner wall. Predictions of incipient downflow of the film, shear stress at the inner wall, and interfacial shear stress were obtained from these measurements. Fluctuations in the velocity gradient at the inner wall were also studied. Results of this study are in fair agreement with previous work and with theoretical predictions based on simplified momentum balance concepts.

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This is the first of a series of monthly reports summarizing the status of the work of the National Accelerator Laboratory. This first report will cover developments since the publication of the Design Report in January. Authorization hearings were held before the Joint Committee on Atomic Energy on February 21, 1968. Dr. Wilson described the plans and designs of the Laboratory. The present plan of the Laboratory is that the Village of Weston will be utilized for office, laboratory, and shop space during construction. The Laboratory business office is already occupying several houses. The linac section is occupying three houses for offices and construction of an 8,000 sq ft laboratory building for linac work is almost complete. Another house is being used and a 4,500 sq ft inflatable building is being constructed for model-magnet and vacuum testing. Other temporary buildings will be constructed for use by other sections. We plan to move into the village as rapidly as is feasible and it is planned that the entire technical staff will be located there by October. The Laboratory staff totals 132 people as of April 1. Of these, 47 are physicists and engineers. Design effort has been somewhat concentrated on architecture …

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Selected values are presented for the high temperature physical and mechanical properties of fuel element materials involved in a loss-of-coolant incident in a boiling water or pressurized water nuclear reactor. The fuel element materials considered are Zircaloy-2 and -4, 304 SS, and UO{sub 2}. Where possible, the property values have been critically evaluated taking into consideration the meltdown environment of steam or steam and air. The physical properties discussed are: melting point, boiling point, heat of fusion, heat of vaporization, vapor pressure, phase transformations, coefficient of thermal expansion, density, total normal emittance, thermal conductivity and enthalpy and heat capacity. The mechanical properties discussed are: tensile strength, ductility, compressive strength, and modulus of elasticity. In most instances, values of various properties are given as a function of temperature to the melting point of the material. The kinetics of the oxidation reactions fo the cladding materials with steam are also discussed and equations presented for calculation of oxidation rates under isothermal conditions for one atmosphere of steam. (auth)

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The biomedical program of the Laboratory of Nuclear Medicine and Radiation Biology for FY 1970 is conducted within the scope of the following categories: Somatic Effects of Radiation; Combating Detrimental Effects of Radiation; Molecular and Cellular Level Studies; Environmental Radiation Studies; Radiological and Health Physics and Instrumentation; Cancer Research; and Selected Beneficial Applications. The overall objectives of the Laboratory within these areas of the Biology and Medicine Program may be summarized as follows: (1) investigation of the effects of ionizing radiation on systems of biological significance and on living organisms; (2) assessment and study of the immediate and long term consequences of the environmental radioactivity on flora, fauna, and man; (3) development of beneficial uses of ionizing radiation and radioactive substances in medicine and biology; and (4) the conduct of training and educational activities in fields related to the biological and medical aspects of radiation.

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