The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.

From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.

The papers prepared and presented by the Atomic Energy Commission and Contractor Personnel are presented. The meeting covered a broad range of problems encountered in the AEC and SS Materials Management work. (W.L.H.)

The following report provides information on an aerosol generator fit to produce fine particles by a vaporization-condensation technique. Included is a diagram of the essential components of the generator.

When the construction of the confinement facilities for Hanford production reactors is completed, the potential for contaminating the environment with accidentally released fission products will be greatly reduced. This was demonstrated already when rupture debris burned in the rear face area of one of the reactors in which the fog spray was installed and ready for service. The fog spray effectively prevented the spread of contamination to the ventilation equipment downstream of the rear face enclosure. Also, the commercially- available absolute filters and charcoal beds will significantly decontaminate the exhaust air, stream of all fission products except the noble gases. Laboratory studies indicate that the filter system should remove at least 50 percent of all fission product halogen vapors and over 90 percent of the particulate matter released from a nuclear incident. In addition, the charcoal beds should provide an additional 90 to 95 percent decontamination of the halogens that manage to pass through the filter. It is not expected that any of the noble gases released will be removed by this system. Laboratory studies, in general, substantiate previous estimates on the release of fission products from overheated uranium fuels. The theoretical estimates are quite accurate for the volatile and …

Uniform, dense coatings of alumina about 5 to 150 mu thick were applied to uranium dioxide particles 44 to 350 mu in diameter by hydrolysis of aluminum chloride vapor in a fluidized bed of the particles at 1830 deg F. The coated particles were resistant to nitric acid leaching, to oxidation in 1830 deg F air, and to thermal cycling from 6OO to 2500 deg F. After low neutron exposures, the coated particles showed excellent fission-gas retention at temperatures up to 2400 deg F in inert gas. Although not optimized in the study, the coating process appears to have commercial feasibility. (auth)

This report addresses the analysis of a rocketdyne report on rockets.

Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.

The objective of the Applied Mathematics Division is to provide mathematical assistance to other scientists in the Lab. This goal is achieved by (1) conducting research in numerical analysis and other branches of mathematics, (2) providing mathematical consultation, and (3) operating a computational service, using both digital and analog machines. Publications, papers, seminars, lectures, and courses are listed. A summary listing of computer programs developed or in progress is given. (For preceding period see AHL-5954.) (W.D.M)

A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)

Ten experimental alloys of aluminum containing up to 4% nickel corroded uniformly, without intergranular attack, when exposed for 3 months to flowing deionized water at 260 deg C. The average penetration rates were between 1.4 and 1.9 mils per month. (auth)

This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.

24p. Bottom-pour Ta and CaF/sub 2/-coated steel melt crucibles for Pu and Pu-rich alloys were developed. The controlled pour is effected by melting a Pu plug in the bottom spout of the crucible after the desired temperature and vacuum conditions are obtained. A description is given of the development of the crucibles which have replaced ceramic crucibles for casting work on the kilogram scale. (auth)

It is necessary to provide the option of using either aluminum or zirconium tubes in the C pile 20-tube overbore test. A bumper-type fuel element has been designed to fit a fixed ribbed aluminum tube size; zirconium tube dimensions were then determined which will provide the same flow and pressure drop when the fuel element is changed from bumper type or self-supported without changing other fuel dimensions.

The IBM-704 program RE-147 is used to calculate the time and space- dependent temperature distribution in a solid cylindrical fuel pin, cooled on the surface, with internal heat generation. The fuel pin may be bare or clad, and its boundary may be cooled by either flowing or staagnat coolant. The heat generatlon source may also be time and space dependent. Specifically, the program considers the fuel pin to be composed of two regions and then solves, by the usual finite difference methods, the heat conduction partial differential equation in the two regions. Simultaneously, the axial and time variation of the coolant temperature is calculated by a finite difference approximate solution of the energy equation for the coolant. An approximate method is included to allow for the effects of solid-state phase changes. In conjunction with the phase- changing procedure, the material properties are permitted to vary from one phase to the next. (auth)

Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution of uranium-- zirconium fuel alloys continued. In corrosion tests to find a suitable container material, Ni was found to be susceptible to a sulfur-type attack. Hastelloy B showed promise, and graphite offers excellent chemical resistance but poor mechanical strength. The dissolution rate of Zr in NaF-- ZrF as affected by impingement of the HF sparge was studied. Production of UF/sub 6/ by fluidized bed fluorination of UF/sub 4/ from ore concentrates was studied. The preparation, melting point, vapor pressure, and vapor density of UF/sub 5/ are given. Preliminary dissolution and recovery runs in semi-works equipment are discussed. Fluidization. Fluidized- bed techniques have been applied to conversion of UO/sub 2/(NO/sub 3/)/sub 2/ to UF/sub 4/ and to calcination of radioactive liquid wastes. Activities of the Green Salt Pilot Plant and shakedown runs of the shielded waste calciner are described. Reactor Chemistry. Studies continued on the kinetics and mechanism of oxidation of U, Th, and Zr. Data are given for oxidation of U in oxygen from 125 to 295 tained C and 20 to 800 mm pressure, and for Zr from 400 to 900 tained C and 200 nan O/sub …

Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg C has been in trouble-free operation for 3000 hrs. Recovery of Pu from Mg solution by distillation of Mg was demonstrated on 1-g Pu scale. The solubility of Th in liquid Cd was measured over the temperature range from 1.9 x 10/sup -3/ per cent at 348 deg C to 1.8 x 10/sup -2/ per cent at 658 deg C. The solubility of Mn in liquid Cd was found to range from 0.27% at 414 deg C to 1.43% at 661 deg C. The solubility of Ni in liquid Cd was measured. The partition of U between liquid Al and liquid Cd was studied as a function of U concentration. The reaction of Al with a liquid Cd solution containing …

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A critical review of the literature revealed no experiments on uranyl ion transfer from an aqueous to a tributyl phosphate phase which positively measured the kinetics of the chemical reaction at the interphase. Drawing isorhythmic lines on a three component diagram gives a complex correlation for the compaction of three sizes of glass beads. Neither the use of thoria sols nor high feed solution concentrations of thorium nitrate gave any significant increase in mean particle diameters over those obtained from nitrate solutions of lower concentrations in flame denitration. A hydraulic film resistance has been detected in the anion exchange of uranyl sulfate into Dowex 2lK, and chloride elution was found to give a higher apparent uranium diffusion coefficient than nitrate elution. The rate of dissolution of mixed thorium-uranium oxides was determined as a function of the per cent of mixed oxides dissolved. Mixing in tanks packed with boron glass Raschig rings is being continued. The SRE hydraulic dejacketer has been operated successfully with prototype fuel rods. Excessive foaming was encountered when sheared stainless-clad UO/sub 2/ was suddenly contacted with boiling 13 M nitric acid. While attempting to shear a prototype Yankee subassembly with Kanigan brazed diffusion bonded joints, a five …

Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel element failure. It was concluded that the discrepancy in measurements is caused by methods not specifying exactly the time for taking radiochemical samples. The data are tabulated as activity and power output, and given as a function of time. A comparison is given of the activities in the primary coolant for April, June, and July of 1958. (B.O.G.)

Samples capsules containing buttons of materials of interest for SNAP fuel elements were held at temperatures up to 1600°F , in hydrogen, under a 20-tsi load for 200+ hours.

In a recent paper, Bowers and Salpeter described a method for calculating the correlation energy of a classical one-component electron gas. The same problem has been considered by Meeron, Friedman, and Abe, using methods involving the summation of cert infinite classes of diagrams. While the relation between these theories and that of Bowers and Saltpeter is not year clear, it is interesting to note that Abe obtained an equivalent expression by approximating an integral. We have calculated the contribution to the equation of state using Abe's original expression and we found that the equation is valid only for certain values and it gives a correction of the wrong sign. On the other hand, our results are comparable to those which Bowers and Salpeter obtain from higher approximations.

The current status of the NPR fuel fabrication and testing program has been reviewed; suggestions have been made concerning areas requiring more information. This report is divided into a series of sections, each of which is a complete entity so a specific problem area can be considered apart from the entire NPR Fuel process. The final section incorporating conclusions and recommendations reaffirms the factors of major importance as well as evaluating those areas which are interrelated. Process problems have been considered from the aspect of manufacturing, not engineering.