Lectures are given in which the nuclear shell model is discussed as a link between the properties of complex nuclei and the free-nucleon interaction. A version of the shell model is derived from nuclear many-body theory, and also this version is compared and contrasted with phenomenological shell theory. Attention is focused on oxygen-18 and fluorine-18. 76 references. (JFP)

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The main values of the 302 gantry exercise were to check the preparation of the Neurospora experiment and the spacecraft loading procedure under timed conditions and to provide final assurance that necessary operations can be completed with appropriate inspection in the allotted time. Because of the brief time interval between the 302 Gantry Exercise and the scheduled Biosatellite A flight, no attempt was made to assay for forward-mutation frequecies; however, biocompatibility tests were performed on the 302 hardware by plating conidia from a number of the modules in the usual fashion to assay survival. The average heteokaryotic conidial survival was 82.6%, which is sufficiently high for use of the conidia in a forward-mutation experiment. Calibration of thermoluminescent dosimeters was carried out using a /sup 85/Sr ..gamma.. source.

Work is reported in these areas: general radiation effects; toxicity of radioelements; studies at the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.

These design elements are described: utility systems; reactor systems; irradiation test systems and facilities; component handling systems; examination systems and facilities; unified instrument and control systems; and other miscellaneous facilities.

Areas of work reported include: general radiation effects; toxicity of radioelements; studies on the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.

The object of the study was the investigation of the behaviour of structures subject to earthquakes. After .describing and analysing seismic movements, useful concepts for earthquake-proofing structures are lintroduced. Then, the dynamic behaviour of systems with n degrees of freedom was studied in order to evolve the theoretical computation of seismic behaviour, a typical application being reticulated structures. The next stage was showing the computational procedure for seismic spectra and the natural frequencies of buildings, an attempt being made to define earthquake-proofing criteria for a special type of reinforced-concrete construction. . The last matter dealt with is elastoplastic behaviour of structures, a study of increasingly growing importance.

In this third semiannual issue, the reactor and power data from the Hanford Production Reactors are shown for the six-month period July through December, 1966, together with the two preceding six-month periods. Experience during the succeeding six-month period will be added in the next semiannual issue. For comparison purposes, the two years of experience will then continue to be shown by dropping and adding a six-month period with each semiannual issue.

All production facilities performed satisfactorily during December, although they were shut down for the Christmas holidays. The Purex SEFOR campaign was completed Dec 21. Redox completed solvent extraction processing of Shippingport reactor blanket fuel elements (PWR); during the first pass of PWR material, an Am-Cm fraction was separated and stored. About 720 kCi Pm-147 and 240 kCi Sr-90 were produced in Purex head end. Two STT casks were loaded with 120 kCi Cs-137 for shipment. Semiworks was used to demonstrate D2EHPA solvent extraction flowsheets for waste. Tests are underway on reduction vessel liners to reduce the crucible material for Pu recovery (two containers used inside vessel).

Preliminary studies utilizing the MOFDA code have been made for tritium production at the K reactors using 33 and 35 grams per foot oralloy (93.5% U-235) in aluminum in conjunction with standard K5N and K5E fuel elements, respectively. For this report, it was assumed that all tritium would be produced in discrete charges of LiAl target elements. It is intended that the study will be extended at some later time to include LiAl splines. The analysis includes the effect of coolant loss on reactivity for hot-or-cold and green-or-exposed conditions for several oralloy loading fractions.

This report details activities of the Division of Production and Hanford Plant Assistance Programs for the month of October 1967.

The results of a statistical study of Columbia River temperature trends were released on October 18 at the Sixth WSU Hydraulics Conference. The new John Day reservoir is under study for possible beneficial effects on flow regulation. Measurements of radioactivity in 396 children were completed at Captain Gray elementary school, Pasco, Washington on October 19, 1967. Measurements began at the Emerson elementary school in Pasco on October 24, 1967, following lectures to the teaching staff and to each of the 18 classrooms in grades 1 through 6. Computer programming was started in October to determine the frequency distribution, mean, and median values of the environmental radiation dose values calculated last month from several thousand individual adult diet records. Response or game bird hunter-employees to a request for participation in a survey of game bird kills during the current season has been disappointing in spite of several articles in the project newspapers.

This report details the borehole examination and inspection results of process tube 2959 following a massive fuel failure and a low flow trip which scrammed the reactor.

Considered herewith are source and special nuclear material composition of ending inventory reports for the month of December, 1966, submitted by the Nuclear Materials Section of the Environmental Health and Engineering Department.

The temperature standard of the new regulation, although less restrictive than previously proposed, continues to be one with which Hanford may find compliance difficult. The degree of restriction will depend both on natural river conditions and the methods of enforcement. Other specific standards are not apt to be restricting in the near future, but will necessitate further study and probably increased routine surveillance. One general requirement, which stipulates that ``all known, available and reasonable methods of treatment`` it must be pursued before approval is granted for a dilution zone, may present difficulties. No guidelines are given for ``reasonable``, yet an adequate dilution zone is mandatory for Hanford reactor effluents to comply with the regulation.

This report discusses a radiation exposure accident of personnel at the Hanford production reactor facilities.

This document details activities of the Reactor Operation Branch during the months of January, 1967 through December, 1967.

During April the N-Reactor operated with a time operated efficiency of 70.8%; and a production availability and steam availability to Washington Public Power Supply System of 68.5%. No fuel element failures occurred. A scheduled outage (April 18 to 25) was used to complete planned maintenance, accomplish the modifications required for the 4,800 Mw power level probe, and for charging the fourth increment of the coproduct demonstration load. Fuel element input production was 100% of forecast. Output production was 110% of forecast, significantly improving finished-fuel inventories and reducing in-process material levels. Calendar-year-to-date output is 102% of forecast. There are now 844 columns of coproduct fuel in the reactor. Two columns of high exposure, 1.96% enriched, coproduct fuel (discharged during March) were examined. These fuels had attained a tube average exposure of 4,094 Mwd/t and operated at uranium temperatures of 550 C to 475 C (temperature range predicted for Mark 5 fuel). Cladding buckling was minimal. The superior performance is attributed to the 800 ppm Al plus 400 ppm Fe uranium alloy. Flow testing of the prototypic Mark 4 fuel continued during the month. Flow split data are being used to redesign the support system to balance the flow in the coolant …

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The extended form of the Jones and Furry theory, which describes the behavior of a multicomponent heavy isotopic gas in a Clusius-Dickel thermal diffusion column, is tested. Experimental and theoretical values of the thermal diffusion column transport equation coefficients Hsub{ik},Ksub{c}, and Ksub{d}, are determined for krypton, a heavy isotopic gas with six isotopes. The experiments are carried out in a column of the hotwire type, at three wire temperatures: Tsub{H}=350 degrees C, 500 degrees C and 800 degrees C. Good agreement is found between the theoretical and experimental values of the coefficients. Seven of nine of the experimentally determined values of the coefficients agree within +- 10% with the corressponding theoretical values. The remaining two experimental values agree within +- 20% with the corresponding theoretical values.

Work is reported in these areas: general radiation effects; toxicity of radioelements; studies at the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.

Safety analysis reports on United States fast and liquid metal cooled reactors were reviewed to gain a better understanding of the safety philosophy applied to the design of these facilities. This information was compiled to help guide the design and safety analysis of the Fast Flux Test Facility. No attempt was made to draw conclusions concerning the relative merit of different approaches and philosophies used by different reactor design teams. The facilities reviewed were; Enrico Fermi Atomic Power Plant (FERMI) Hallam Nuclear Power Facility (HALLAM) Southwest Experimental Fast Oxide Reactor (SEFOR) Fast Reactor Test Facility (FARET) Experimental Breeder Reactor No. 1 (EBR-I) Experimental Breeder Reactor No. 2 (EBR-II) Fast Reactor Zero Power Experiment (ZPR - III). The information gathered from the safety analysis reports is tabulated under these headings: Control and Safety Systems; Reactor Protection Systems; Backup Systems; Containment or Confinement Systems; Inherent Reactivity Effects and Important Physics Parameters; Fuel and Fuel Handling; Accidents Considered and Chemical Problems; Site; Exhaust Ventilation System; and Waste Effluents.

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This is a progress report on analysis of thermal data from the Black Rock Desert of northwest Nevada. Hot springs at Soldier Meadows, Fly Ranch, Gerlach, and Pinto Mountains were mapped, and water flows and temperatures measured, by G.W. Berry and G.R. Downs in 1965 and 1966. These data have been studied further by Frank Hadsell (geophysicist) and L.T. Grose (geologist) at the Colorado School of Mines and with the computer facilities of the School of Mines Graduate Research Center, in an effort to determine geothermal power potentials. Power generation by hypothetical Carnot engines has been calculated for the four thermal areas. Data from seven prospect holes at Pinto Mountains have been exploited in plotting geothermal gradients and computing heat flows. It is emphasized that this report is to a large extent an exercise in arithmetic and thermodynamics, fraught with assumptions that may not endure. All of the conclusions are tentative. However, they consider this a valid line of practical research. To the extent that the figures and conclusions are applicable, they are generally encouraging in themselves and in comparison with those of developed geothermal areas, as to the geothermal power potential of Sun acreage in the Black Rock Desert …