Activities in a project aimed at the improvement of fuel elements for high flux test reactors are reported. The investigation of new fuel compositions, distributions, and geometries is being undertaken to increase fuel life, to improve the flux distribution, and to provide a means of safely reaching higher reactor operating power and power density in these reactors. The effects of nuclear irradiation on the fuel and structural materials is being studied to predict the performance of these materials in more advanced reactor designs. A summary of the past year's progress is given and the fabrication and irradiation of samples containing up to 50 wt % U--Al alloys, cermets of UO/sub 2/, U/sub 3/O/ sub 8/, UC, UN, U/sub 3/Si, and Al, clad in various Al an d Be--Al materials is described. The use of ThO/sub 2/ and Th cores, the addition of BeO to cermet cores and high density fuei cores of U--Al intermetailics produced by powder metallurgy techniques were studied during the year. High strength APM claddings involving Al/sub 2/O/sub 3/ contents from 8 to 10% were tested and indicate the need for improved quality control of the APM material. Duplex claddings involving burnable poison layers and APM clad …

Information of interest to analytical chemists is presented in a report containing both positive and negative results obtained in a total of 58,467 determinations. The data and information are presented in sections concernlng the work of the shift laboratory, special analysis laboratory, spectral analytical group, analytical development group, quality control and standards laboratory, and analytical service for EOCR. Details of methods added to the ICPP analytical manual, and to the ICPP analytical radiochemlcal manual are included. (J.R.D.)

The research program at Brooknaven is described. Current activities in physics, high-energy accelerators, instrumentation, chemistry, nuclear engineering, applied mathematics, biology, and medical research are outlined. (D.L.C.)

A total of four sections containing technical data is included in the report. Separate abstracte were prepared for each section. (J.R.D.)

HW-70780, {open_quotes}An Operational Reactivity Accounting System Based on One-Group Diffusion Theory{close_quotes} describes a reactivity accounting system which is an improvement over the present {open_quotes}flux-squared weighting{close_quotes} system. Several changes and additions have been made which will simplify and increase the accuracy of the system described in the parent document. The changes occur primarily in the application of the system and are compatible with diffusion theory and the parent document. Each change will be described briefly and to illustrate their application an example reactivity balance, using the reactivity accounting system, will be performed.

Nuclear Science Series'' of the National Research Council. Committee on Nuclear Science. The use of vacuum distillation of inorganic compounds and metals for radiochemical separations is reviewed. A brief description of the experimental apparatus which is most often used for the distillation is outlined. Advantages and disadvantages of the various techniques are discussed. Detailed separation procedures are described for wet chemical distillation separations as well as for separations of daughter radioactivity from target materials by direct heating of the target. (auth)

The results of a study of the installation and operational characteristics of a SNAP reactor system integrated with a manned space station are presented. The reference system selected was an 11 kw(e) version of a SNAP 2 system employing multiple power conversion units coupled to a single reactor source. Of prime importance is the reactor radiation shield required for the manned system and the use of design features which minimize the shield weight. The weight of the radiation shield is highly dependent upon the geometrical configuration of the space station and the reactor since shadow'' shielding of the manned compartments is required for minimum weight systems. The installation and shielding requirements of the 11 kw(e) system were considered for two types of space station configurations; one was a 10 ft dia cylindrical station with a reactor separation distance of 50 ft and the other a 150 ft dia toroidal station with the reactor located in the hub. The weight of the power system installed in the cylindrical space station was about 9000 lb of which 6000 lb was required for shielding. The weight of the system for a toroidal station was approximates 25,000 lbs of which 20,000 lbs was required …

Wax lap preparation for the vibratory polisher consists of melting the wax, pouring it into the bowl, and allowing it to solidify. The wax adheres to the bowl without difficulty. Specimens to be polished were mounted in bakelite or lucite. Grooves formed in the surface of the way can be removed by melting with hot water. (R.J.S.)

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Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)

The status of aqueous processing methods for thorium fuels is summarized, with principal emphasis on the stainless steel-clad ThO/sub 2/UO/sub 2/ type. Data were obtained principally from laboratory-scale experiments with fully irradiated fuel samples and engineering-scale tests with unirradiated fuel. Stainless steel cladding was easily dissolved with 4 to 6M H/sub 2/SO/sub 4/ (Sulfex process) or 5M HNO/sub 3/-2M HCl (Darex process) in LCNA (Nionel type) or titanium equipment, respectively, in semicontinuous or batch equipment. Uranium losses to the decladding solutions were approximates 0.3% and 3 to 5% for the Sulfex and Darex processes, respectively, with fuel irradiated to approximates 20,000 Mwd/ton of core. The uranium was readily recovered from the Darex decladding solution in the acid Thorex extraction process. The ThO/sub 2/UO/sub 2/ core was dissolved in 13M HNO/sub 3/ -0.04M NaF-0.1M Al(NO/sub 3/)sub 3/. Uranium and thorium can be recovered from graphite-base fuels by disintegration and leaching with 90% HNO/sub 3/, grinding and leaching with 70% HNO3, or combustion followed by dissolution in fluoridecatlyzed nitric acid. Uranium and thorium were recovered from nitric acid solutions and separated from fission products by extraction with 30% tributyl phosphate in Amsco in the acid Thorex process. The use of an acid …

The status of aqueous processing methods for Th fuels is reviewed. A specially designed 320 ton shear was successfully tested for chopping full size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths. Pieces about 0.5-in. long are preferred since the core pellets are more severely crushed during the chopping operation, and consequently, the rate of core dissolution is enhanced. The Darex (dtlute aqua regia) and Sulfex (4 to 6 M sulfuric acid) processes for dissolution of stainless steel claddings were developed on a small engineering scale with unirradiated fuel. In hot cell tests on stainless steel clad ThO/sub 2/-UO/sub 2/ fuel pins irradiated up to 22,000 Mwd/ton of fuel, the core pellets were severely fractured and losses of U and Th to the Sulfex and Darex solutions were approximates 0.3% and 3 to 5%, respectively. The latter losses are easily recovered in the extraction system. U and Th can be recovered from graphite base fuels by burning and dissoiution of the ash in HNO/sub 3/ or by grinding to approximates 200 mesh followed by HNO/sub 3/ leaching. The Acid Thorex extraction process was developed to recover both U and Th using tributyl phosphate (TBP) as the solvent and …

This memo is distributed to acquaint personnel with (a) the status of the various 410 areas, (b) time and personnel required to do optic experiments in the ``Dog`` area, and (c) status of the timing and firing system and conditions of cables from Able to Dog.

Separate abstracts were prepared on the 12 sections of this report. Abstracts covering 4 sections have previously appeared in NSA. A list is included of staff publications during the period covered by this report. (C.H.)

Research progress at Argonne Cancer Research Hospital is reported in 23 papers. Separate abstracts were prepared for 12 papers. Eleven papers were previously abstracted for NSA. (M.C.G.)

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Dual neutron diffractometers were designed and built for use at the CP-5 reactor with a number of special features: (1) Two monochromntors are used in an in-line arrangement, as suggested by Levy and Peterson, utilizing the same primary beam with two independent diffractometers, one a horizontal instrument and the other a vertical unit. (2) The two monochromnting crystals may be used in transmission or reflection, and each crystal may be accurntely positioned by external controls. (3) Considerable variations in the wavelength of the primary beam may be made for both diffractometers by changing the take-off angle from the monochromator crystals by means of interchangeable pie-shaped segments. (4) The monochromating crystals are located inside of a relatively small, heavily shielded housing which consists of lead, steel, Boral, and depleted uranium walls which have slotted holes for the exit of two beams, one for the horizontal and the other for the vertical unit. (5) The monochromator housing is surrounded with a large moderating shield which consists of stacked 2-in.thick Masonite die stock forming a 4-ft cube with a minimum thickness of 2 ft from the inner housing. (6) The detector arm on the horizontal diffractometer pivots about the center of the diffractometer …

A publications list, incorporating a subject index was compiled by machine methods. The publications covered are those originating at Argonne but published elsewhere. The list is arranged alphabetically by author's names and covers the period from July 1, 1961 through June 30, 1962. The subject index is a key word in context index using the title. (M.C.G.)

The Argonne Thermal Source Reactor is a highly enriched, light-water- moderated thermal reactor. Movable shielding allows complete access to one face of the core. There is ready access to the central and 2 peripheral core locations, and it is possible to thrust samples with small reactivity effects into these locations. The reactor was approved for operation at 10 kw. Design and construction details are described to aid present and potential users of this facility. (auth)

Research and development on metallurglcal aspects of pressurized-water systems is summarized. A survey was made of the methods of determining fuel burnup. The mechanisms and kinetics of the loss of boron during heating at 1135 deg C in various dynamic environments were determined. A model was developed to quantitatively characterize the UO/sup 2/ dispersion microstructure of roll-clad fuel plates relative to an ideal'' dispersion. In order to avoid the loss of boron from UO//sub 2/- stainless steel dispersion fuel plates during fabrication, studies were carried out on a refractory glass containing 4 wt.% B/sub 2/O/sub 3/. By using lowsilicon elemental powder, the undesirable reaction between Eu/sub 2/O/ sub 3/ and Si was eliminated; and 13 full-size SM-1 absorbers were fabricated. Work was continued on the borongradient neutron absorber concept. A design was studied for preparing a composite control rod having an upper section made of a boron-gradient dispersion and the lower tip made of Eu/sub 2/O/sub 3/ and stainless steel. Two fuel elements were examined after significant exposure in SM-1. The examination of the miniature boron-iron samples in the final phase of the MTR irradlation test was performed. Twelve miniature test specimens containing 20, 30, or 40 wt % Eu/sub …

This report details benefits of an increase in the flow of water from the lower depths of Grand Coulee Reservoir which used to lower river temperatures at HAPO. A net average daily reduction of over 1.7{degree}C resulted at HAPO. The peak reduction was over 4.0{degree}C. The net production gain from temperature change was 13,350 MWD. The cost of control was: Grand Coulee Charges (Estimated) $37,000, and other 3,500, for a total of $40,500.

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Preparation of enriched fuel elements and target (N) elements for a full H-Reactor E-N demonstration loading was authorized in April, 1960. The objective of this loading was to demonstrate the feasibility of operating a Hanford reactor economically as a plutonium-tritium producer to increase over-all conversion ratio and diversify product output. Irradiation of the E-N load began in May, 1961 and was completed in January, 1962.

Experimental studies of the relative atomic mu --meson capture probabilities in the constituents of chemical compounds are described. Fermi and Teller had predicted that the atomic-capture probability is proportional to the nuclear charge of the atomic species weighted by its atomic concentration. This is sometimes referred to as the Fermi-Teller Z law.'' Previous experiments indicated no clear systematics to this capture process, and there are conflicts between the results of several measurements made with the same or similar compounds. In these experiments the capturing atom was identified by detection of either mesic x rays or decay electrons from mu /sup -/ mesons bound in the mesic K shell in the atomic species, In these experiments oxides and sulfides of some medium- and high-Z elements as well as two metallic solutions were used, and a nuclear capture product (neutron) rather than the decay electrons was detected. Results show that among the substances examIned, namely CuO, Sb/sub 2/O/sub 3, PbO, CuS, Sb/sub 2/S/sub 3/, PbS AgLi, and CuAu, the Z law'' behavior is not indicated either in insulators or in metals, although in all cases there is a preference for capturing in the atom of higher Z. If the atomic-capture probability is …