The pile physics group reports on reactivity power coefficients from the production test No. 105-248-P, the water leak in B pile, graphite properties, xenon equations from the B pile shutdown of March 1946, and reactivity balance. The experimental physics group headed by J.M. West reports on graphite testing, the P-11 project, and shielding. The experimental physics group headed by E.B. Montgomery reports on diffusion length measurements in the DR and H piles. (GHH)

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The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 6OO deg F. Quenching from 6OO deg F or above gives high impact strength, as does removal of hydrogen by hightemperature vacuum aanealing. The evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilbrium pressure of hydrogen in zirconium the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium are discussed. (auth)

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This report, for July 1957 from the Chemical Processing Department at HAPO, discusses the following; Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

A previous investigation concerned with liquid-core fuel elements and the materials from which they could be constructed revealed tht an alloy of U--5 wt. % Nb had considerable promise as container material. Results are given from a further investigation of this alloy, as well as another containing 10 wt. % Nb, to determine the time and temperature limits within which tbe oxide layer remains protective, the factors which hasten or delay the breakdown of the film, and the mechanism whereby the film deteriorites, (auth)

The July, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

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Two methods for extrusion cladding were investigated and evaluated. In the coaxial method, the component parts of the extrusion assembly are concentric, and the fuel plate moves in the same direction as the hydraulicpress ram. In the right-angle method, the fuel-plate metion is perpendicular to that of the ram. Ribbed sheaths of aluminum were extruded satisfactorily on 3-in.-wide uranium plates in lengths up to about 10 ft. Lowest extrusion pressures were achieved with the most streamlined designs of mandrel tips, using flatfacod shear dies. Good results were obtained with billet and die temperatures of about 1050 deg F, at extrusion speeds up to 60 ipm. Extrusion pressures were 25,000 to 60,000 psi. End-cladding procedures were developed which involvod attaching end plates machined from aluminum powder-metallurgy products (12 to l8 wt. % Al/sub 2/O/sub 3/) to the core by means of T-shapod joints, and cladding the entire assembly with aluminum. Excellent bonds were achieved, on uranium as well as on the end plugs. The median values obtained by stud weld tests were 26,000 psi for uranium, and 12,000 psi for the end plugs. The importance of proper tool alignment and avoidance of imbalance of forces caused by pressure differentials within the …

The differences in the sizes and shapes of crystals formed during four common types of thermal gradient mass transfer experiment are discussed These difference are illustrated with photograped for each case considered. A mechanism is advanced to accoutn for the of mass transfer experiment. Based on an idealized icting the stabe under various experimental conditions. Numberical n graphical form. (auth)

Evidence is presented that the hot-zone attack of nickel-base alloys in contact with fused fluorides occurs by a grain-boundary diffusion process. Predictions based on tbe grain-boundary diffustion model are shown to copmpare favorably with existting data. Certain anomalies are pointed out with regard to the corrosion of Inconel by Fuel No. 20 (NaF-UF/sub 4/-ZrF/sub 4/) and tests which would lead to a better understanding of fused-salt corrosion are outlined. (auth)

A study was made to determine the magnitude of the velocities existing in the various slurry pumps currently in use and to determine possible methods of reducing the velocities in order to obtain longer life. The maximum velocities of the lOOA, 200A, and 300A pumps are between 39 and 53.6 fps with the exception of the lOOA absolute discharge velocity which is 80.6 fps. For large slurry pumps, it is recommended that lower speeds be used in order to reduce the impeller relative velocities. (auth)

Production of Pu nitrate from separations plant during this month was below forecast. UO{sub 3} production, shipments met schedules; so did unfabricated Pu shipments. Purex plant was stopped to replace the final waste concentrator (F-11) (leak). Two Pu-U partition failures were attributed to foreign organic material in the nitric acid; the Pu product was kept within specifications by adding NaF and ANN to ion exchange feed stream. A Np recovery run was started in Redox, and dissolution was started of 12 special 2-ton test batches of normal U fuel elements, irradiated to provide information on Pu formation rates. The damaged B-2 E-metal dissolver was replaced with a conventional dissolver. Test of a new sieve plate cartridge in Recuplex H-1 extraction column was stopped. A new semi-continuous product concentrator-stripper was made to replace Recuplex batch concentrator. Conversion of Purex prototype anion exchange to a manufacturing unit is nearly complete. Design was completed on the new Redox E-metal dissolver. Process feed was introduced into RMC button line and 3 buttons made. Project proposal for NPF reprocessing was revised.

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission gas released, the internal pressure, the cladding strain when the internal pressure exceeds the coolant pressure, and the creep damage was used for comparing top-loading and inventedloading fuel programs for the EGCR. A statistical method was developed for estimating the probability that the hot spot on the EGCR fuel element will exceed a given temperature. A method of cooling the EGCR control rods was developed that will minimize diversion of coolant flow through leakage paths between graphite blocks. A preliminary design of a control rod cooled by this method was developed. Means for reducing the thermal stresses in the top head nozzles of the EGCR pressure vessel were studied. The stresses in the graphite sleeves of the EGCR fuel elements were calculated, and the maximum stress was found …

Studies on the use of coagulant aids in the lime-soda treatment of large- volume, low-level radioactive liquid waste revealed that a combination of Hagan Aids No. 50 and No. 18 gave fairly good results under most conditions. The effects of feed solution concentrations, mode and point of addition, and water temperature were studied. (C.J.G.)

As the first part of a study to evaluate the economics of the various steps leading to and including the permanent disposal of high-activity liquid and solid radioactive waste, costs of interim liquid storage of acid and alkaline Purex and Thorex wastes were estimated for storage times of 0.5 to 30 years. A 6- ton/day plant was assumed, processing 1500 tons/year of uranium converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/year of thorium converter fuel at a burnup of 20,000 Mwd/ton. Tanks of Savannah River design were assumed, with stainless steel construction for acid wastes and mild steel construction for neutralized wastes. The operating cycle of each tank was assumed to consist of equal filling and emptying periods plus a full (or dead) period. With interim storage time defined as filling time plus full time, tank costs were minimum when full time was 40 to 70% of the interim storage time, using present worth considerations. For waste storage times of 0.5 to 30 years, costs ranged from 2.2 x 10/sup -3/ to 9.5 x 10/sup -3/ mill/kwh/sub e/ for acid wastes and from 1.7 x 10/sup -3/ to 5.1 x 10/sup -3/ mill/kwh/sub e/ for neutralized wastes. …

Cratering is a subject that has been studied by many investigators for many years for many purposes. These purposes range from experimental studies of physical properties to large scale excavations using explosive charges of kiloton size. In the past ten years considerable effort has been devoted to cratering experiments for the purposes of determining the effects of cratering by nuclear explosions, with recent accent on Plowshare applications. From the large amount of data available for craters in alluvian has been possible to establish very reliable relationships between charge size, depth of bursty crater radii, and crater depths. In addition it has been possible to construct a preliminary theory of the mechanics of explosive crater formation. The available experimental data for nuclear and high explosive craters are reviewed, with particular emphasis on the data for desert alluvium, and the pertinent relationships are derived. A theory of the important cratering mechanisms, which has been evolved on the basis of these data and data from other sources, is outlined. (auth)

Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-80001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved, as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify that the nickel-plate integrity problem has been solved by irradiating a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis.

In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta heat treat facility and autoradiograph film developer. Manpower savings will result principally from refinement of each operation. There are no really outstanding areas for improvement. The greatest potential for savings is in material costs. These are illustrated in Tables I&IV. Maintenance costs provide for possible significant reductions at braze, vacu-blast, nondestructive test, autoclaves, and chemical processing equipment.

At 10:59 AM (PST), Saturday, April 7, 1962 a criticality accident occurred in a plutonium waste chemical recovery facility at the Hanford Atomic Products Operation, operated for the Atomic Energy Commission by the General Electric Company. Four men were hospitalized but were released after medical observation and after estimates of the radiation doses received were available. This report describes the dosimetry investigation that was made following the accident. This investigation was facilitated by the fact that all employees affected had personnel dosimeters in their possession when the incident occurred. The interpretation of the data supplied by these dosimeters was supplemented by information gathered by techniques that were developed in connection with other accidents. Below, the available information is first presented and then applied in a discussion of the dosimetry of the people involved in the accident.

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This report, from the Chemical Processing Department at HAPO for July 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.

The perturbation metheds used to obtain a relative plot of the electric field and the value of R/Q are described. A method involving radial pulling of dielectric and metallic beads is proposed for the R/Q measurement. The experimental data are shown to agree with the previously presented theoretical predictions. (D.C.W.)