Progress was made in the following areas: FIM (field ion microscopy) studies of defects in W irradiated with W ions or electrons; FIM studies of Au irradiated with Au or Xe ions; FIM and electrical resistivity study of vacancy defects in quenched W; FIM studies of dilute Pt alloys; measurement of the range of focused replacement sequences in Au; investigation of grain boundary strtucture (using Au); FIM observation of dissociated screw dislocations in Mo; calculation of properties of point defects in metals; and atom probe FIM. (auth)

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A fluidized, countercurrent ion-exchange system was developed, operated, and evaluated by the Bureau of Mines in support of its objective to help assure an adequate uranium supply for future national needs. The system consisted of integrated multiple-compartment absorption and elution columns in which the solution flows are continuous, except for short periods when resin increments are withdrawn. The exchange of uranyl sulfate between a simulated acid-leach-uranium solution and a strong-base, ion-exchange resin was studied, together with subsequent elution using an acidified sodium chloride solution. The effects of the number of compartments, compartment height, amount of resin withdrawal, solution flow rate, and column diameter were investigated. Also examined were the kinetic and equilibrium relationships for the absorption and elution steps. The experimental data indicate a strong interdependence between variables. Solution retention time appears to be a major limiting variable in the absorption process, while resin residence time is the determining factor in the elution process. The columns system was efficient over a range of conditions, but close control was needed for optimum operation.

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The permeability (anti P) and diffusion coefficient (D) of the gases H/sub 2/, Ar, Kr and Xe have been measured in certain elastomer materials of interest to the FFTF/CRBRP Cover Seal Program. These elastomers include Buna N, Buna S, Butyl Rubber, ethylene-propylene polyacrylic, polyurethane and silicone. Measurements were made over the temperature range 100 to 300/sup 0/F. Data for the permeability and diffusion coefficient for these gases in the above elastomer materials are given. The method used also yields data for the solubility of gas in the elastomer; however, these data are less precise than data for anti P and D.

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The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels.

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Disposal of tritiated water in a gas well is reported. The gas production, water disposal, and sampling history of the well are briefly reviewed. Blowdown testing of the well is reported. (LEW)

A section of notes on geothermal exploration using the resistivity method precedes the main body of the paper. Field data from the Broadlands Area of New Zealand, Java, and the Imperial Valley, California are included. The reconnaissance resistivity survey recently completed in the East Mesa Area confirmed that a broad zone of low resistivities at depth extends through the area in a NNW direction. The interpretation of the resistivity data and the location of the resistivity lows at depth is much less definite in the Imperial Valley than it is in other areas of geothermal exploration. This is due to the extremely low background level of resistivities. The low resistivities in the Imperial Valley are due to the high porosity of the sediments and the high salinity of the solutions contained within the rock. The expected decrease in resistivity due to elevated temperature is much more difficult to detect in this environment. Edges of the zones of low resistivities have been delineated in almost all directions. (JGB)

The key experimental and analytical studies which have led to our present understanding of the mechanisms of ductile fracture are reviewed. It is concluded that insufficient progress has been made in the quantitative description of ductile separation mechanisms on a microscale to allow the realistic prediction of fracture toughness from material properties and microstructure. An experimental study of ductile fracture is underway which has the aim of determining the growth rate of voids in known plastic deformation fields as a function of triaxiality of stress and material work-hardening. Novel specimens of particularly well characterized microstructure are utilized.

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The objective of this study is to demonstrate the applicability of a radioisotope heated Mini-Brayton power system to the 1973 USAF/AEC requirements established for the SURVSATCOM Mission. The principal requiremenets of the power system, are: 400 We power level; maximum weight 205 lbs.; $1.2 to 2.0 million per unit cost; and 5y mission duration. A radioisotope heat source that meets the ACE Nuclear Safety Criteria is presented. The major aspects of the Reference Design MB-ERTG are summarized. The Reference Design, utilizes a flexible Brayton rotating unit (BRU), a /sup 244/Cm heat source with ceramic clad fuel cylinders and an aluminum radiator. The flexible BRU has a variable power output capability, from 400 We to 3000 We, and is an important factor in the formulation of a cost effective development plan. The system weight is 186 lb and unit cost, including the /sup 244/Cm fuel, acceptance testing and delivery is $748,000. The total development cost for the 5-yr program is estimated at $16.4M with an additional $6.5M required for /sup 244/Cm heat source development support, /sup 244/Cm fuel, heat source fabrication and capital equipment expenditures. (LCL)

The objectives of this program are to conduct the development and testing necessary to produce reliable and adequate handling devices for core components for an LMFBR plant utilizing under-the-shield refueling and reactor vessel cover rotating plugs. Component performance in the following three specific areas of concern will be investigated: (1) a reliable rising stem, vertical motion, in-vessel transfer machine (IVTM) for use in an under-the-shield refueling system with multiple rotating reactor vessel covers, (2) and ex-vessel transfer machine (EVTM) for off-line removal of fuel from the reactor in-vessel storage, and (3) ancillary fuel handling equipment, such as auxiliary handling machines (AHM), floor valves, and core component service equipment.

We propose to search for direct muon production in the forward direction from 300 GeV protons incident on a heavy nuclear target. By using the first stage of the Ml beam as a source of a diffracted proton beam and the second and third stages of Ml as a spectrometer, one can make a measurement of the direct muon to pion ratio at values of x between 0.3 and 0.75. If this ratio is on the order of 10{sup -4}, the event rates are on the order of 800 direct muons/hr. at an x of .5. The modifications to the Ml beam are minor.

A report about the United States's coal supply. The U.S. has 25 percent of the world's identified coal resources and about 20 percent of the world's estimated total coal resources.

The phases of the 1974 geothermal field tests at the Niland Reservoir in the Imperial Valley of California are documented. The following tests are included: separator, steam scrubber, steam turbine, heat exchanger, packed heat exchanger, corrosion, chemical cleaning, and control and instrumentation. (MHR)

The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configuration provide acceptable fission product and cover gas retention capabilities at LMFBR Clinch River Plant operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the LMFBR Clinch River Plant to support the national objective to reduce all atmospheric contaminations to low levels.

Sixty-seven human subjects with normal testicular function were subjected to acute testicular irradiation in doses ranging from 8R to 600 R. Post irradiation observations included sperm counts and morphology, and radioimmunoassays for levels of reproductive steroids and hormones in urine (later plasma). Preliminary results and irradiation procedures are tabulated. An overview and analysis of results to date is published in a separate communication. (ERB)

All of the available analytical results from the 8 sediment cores and 16 water samples obtained from water bodies in the vicinity of Mound Laboratory during July 1974, are reported here. These include /sup 238/Pu in both sediment and water, /sup 241/Am in sediment and /sup 3/H in water. The quality of these analyses was found to be acceptable with the exception of an approximately 30% bias in the accuracy of the /sup 238/Pu data.

Crucial and limiting engineering and materials problems associated with the design of an MHD steam bottoming plant are discussed. Existing experimental and theoretical results on corrosion, fouling and deposits, potassium seed recovery and regeneration, are reviewed. The state of knowledge regarding the design of heat recovery and seed recovery units for coal-fired MHD plants is inadequate at the present time.