The commercial feasibility of the electrolytic process for Th production has been demonstrated. The cell produced 7 lb. of good quality metal per hour. A cathode cooling system was developed. The major construction materials, Ni and graphite, were satisfactory. The process yield was 86%. (T.R.H.)

This is the monthly report of the Hanford Laboratories Operation, March, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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An experimental program was initiated io determine the extent of fast neutron and gamma ray streaming through the SRL Mark II control and safety rods and to evaluate the adequacy of the shielding provided in these control and safety rods. The methods and procedures used to evaluate these problems are routine and proven for determining gamma-ray and fast neutron dosages using radiation sensitive films and gold foils. The final experimental results indicated that no excessive streaming of either gamma rays or fast neutrons is present above or around the SHE Mark II control and safety rods. The analytical attenuation methods used to calculate the fast neutron and gamma-ray streaming dose rates gave results that compared favorably with the experimental data. Even ihough the agreement was favorable, it cannot be concluded that these analyical methods would be equally valid for other annular geometries. Additional experimental work will be necessary in order to establish the validity for performing similar analysis, but the favorable agreement encourages the use of such methods until other methods are determined. (auth)

The Battelle Research Reactor is a modified pool reactor located in a sparsely settled 500-acre tract owned by Battelle 13 miles west of Columbus, Ohio. The reactor has been operating since October 29, 1956, at power levels up to 1 megawatt. More than 300 megawattdays have been logged on the reactor with most of this operation at a power level of 1 megawatt. No serious incidents have occurred during the operation of the reactor. With only a few modifications the reactor will operate continuously at a power level of 2 megawatts. First, interlock will be added to the safety instrumentation to scram the reactor in the event of significant reduction in the flow rate of the primary coolant. Second, to provide additional margin of safety against the possibility of local boiling occurring in the core, the primary flow rate will be increased to greater than 1500 gpm. Third, a 700-gallon holdup tank will be added to the primary coolant system to allow for decay of the nitrogen16 formed in the coolant as it passes through the core. Holdup will reduce the dose rate at the surface of the pool to 4 mr per hr or less during routine 2-megawatt operation. …

The purpose of this work was to investigate the possibilities of producing a plastic bonded explosive having greater mechanical strength than that of presently existing plastic bonded explosives. This interim report details activities and progress through July 15, 1957.

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Tests performed to determine the hazard associated with the inhalation of radioactive materials as the result of smoking with contaminated hands indicate that for dry uranium compounds adhering to the palmar surfaces of the hands, approximately 1.0% of the material may be transferred to a cigarette, and that of this approximately 0.2% may appear in the smoke which is inhaled. Most of the contamination originally placed in a cigarette was found in the ash, and only 11% of the material was not recovered following burning; approximately half of this loss may be attributed to normal losses inherent in the analytical process, the recovery efficiency for which was found by supplementary experiments to be 95%.

A summary of the Cr data from the HRP in-pile corrosion program is examined in an effort to determine the Cr species present in such solutions under in-pile conddtions. Data from previous in-pile bomb and loop experiments pertinent to Cr behavior are tabulated, and correlations are offered to support a proposed model. It is pointed out that other interpretations of the same data are possible, and to obtain conclusive evidence as to the identity of Cr species in these solutions, especially designed experiments are necessary. (J.R.D.)

A description of hot laboratory metallography and techniques of operation are presented. These facilities and techniques provided a means of examining fuel elements that contain UO/sub 2/ after irradiation to high burnups. Some unusual irradiation characteristics of UO/sub 2/ were observed, and each effect is discussed. A complete explanation of the causes of such effects has not yet been obtained. (auth)

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The advantages, disadvantages, and cost of constructing a auclear power reactor underground are outlinedData on underground construction of hydroelectric plants, other structures, and underground reactor projects in Norway and Sweden are reviewed. A hypothetical underground Experimental Boiling Water Reactor design and sketch are given with cost estimates(T.R.H.)

This report gives a brief summary of work at Battelle in support of Savannah River reactor fuel elements. Barrier effectiveness tests show that 0.2 mil nickel is a minimum for diffusion barrier application. Successful bonds by roll cladding with an electrodeposited nickel bond layer have been produced without deformation of 1 inch x 1 inch x 0.180 inch cores. Deformation of core versus pack has been established for several conditions of core dimension and rolling schedule. Apparatus for a critical extrusion test is being machined. The experiment is planned for late October. Beryllium additions to the AlSi bath suppress drossing, but they have negligible effect on intermetallic compound formation. Corrosion test failures of soldered ribs sprayed with zinc took place in 6 days regardless of solder used. The same ribs sprayed with aluminum are still intact after two weeks. Solder bonding with a flash coating of copper on both core and sheath has been satisfactorily completed with aluminum and uranium.

ABS>A hypothetical reactor core is presented in which right cylindrical fuel regions sre positioned at the core corners of equilateral, space-filling, parallelograms. The average gamma heating rate density in each of a set of concentric annular regions, centered on a fuel cylinder, is presented for three different fuel cylinder separation distances. The fuel cylinder radius, fuel composition, and moderator composition are held constant. The calculation was done using the Monte Carlo method. (auth)

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The feasibility of the Liquid Metal Fuel Reactor (LMFR) proposed by Brookhaven National Laboratory as a source of electric power was thoroughly investigated. The reference design is based on an LMFR using U dissolved in Bi as the fuel and a thorium bismuthide in Bi slurry as the blanket. Detailed estimates of power costs are presented for electrical power stations from 226 to 904 Mw net electrical capability. (C.W.H.)

The difference in rates of reaction of isotopic molecules may be utilized to produce appreciable isotope enrichments. When a competitive irreversible isotopic reaction is carried out to a high extent of completion, the residual unconverted substrate becomes exponentlally enriched in the heavier isotope. In deuterium systems, a substantial function of the D inventory is retained in the enriched residual substrate, so that conversion of the depleted product is unnecessary. For isotopes of heavier elements such as C/sup 13/, N/ sup 15/, and O/sup 18/ the retention is low, so that product conversion and recycling is desirable unless the starting material is of negligible value. Experiments are described in which enrichments of C/sup 13/ have been obtained using the reaction rate principle in dehydration of formic acid and hydrolysis of urea. Procedures are given for the preparation of decimolar barium carbonate at the level of 1.6% C/sup 13/, and molar barium carbonate at the 1.4% level starting with commercial materials. (J.R.D.)

The techniques used in sampling, analyzing, and evaluating results for determining hazards from external radiation, airborne radioactive material, radioactive contaminants in mill effluents, and urinary uranium, as applied to the Monticello, Utah, uranium mill, are described. Corrective measures used by National Lead Company, Inc., at the Monticello Mill are described along with the results from later surveys which showed large reductions in the potential radiation hazards. Details are given of the methods used to determine personnel exposures to radioactive and silicosis-producing dusts, potential external radiation hazards and in assaying mill effluents for uranium and radium, assaying urine samples for uranium, as well as the standard operating procedures issued at Monticello to employees for preventing and/or controlling personnel exposures. (auth)

The casting of shapes of uranium--molybdenum metal of varying sizes and thicknesses from a molten charge has been successfally accomplished with specificially designed graphite distributors and molds. Solid cylinders, hollow cylinders, and flat plate shapes were cast in gang molds. As many as 35 solid cylinders have been cast simultaneously. All castings had smooth surfaces, and solid shapes were cast to 0.006-in. tolerance on all dimensions except length. (auth)

An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)

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