Progress on an isotope-fueled auxiliary power unit is reported. Based on the power requirements of 260 W, it was concluded that Ce/sup 144/ should be used as fuel. Estimates were made of fuel availability and unit cost and weight at power levels of 133, 300, 500, and 1000 W(e). Fuel development, boiler development, system and operational considerations, and the power conservation system are discussed. (M.C.G.)

Bubble size measurements in the foam column showed that a spinnerette with 50 mu holes gave a nearly normal distribution of bubbles sizes while a coarse fritted glass gas sparger had a tail of large bubbles which did not fit the normal curve. A set of equations solvable by a finite difference technique are presented which completely describe the irreversible reaction rate of H/sub 2/ or CO with a fixed bed of CuO pellets. Radiation damage tests are in progress to evaluate plastics for the Transuranium program. All dejacketed SRE Core I U fuel slugs were reeanned and shipped to Savannah River. Installation of the shear-leach complex is complete. The shortest practical length into which a tubular fuel element assembly may be sheared appears to be 1/2 in. Tests showed difficulties with shearing assemblies containing tube sheets. The stepped shear blade used for Mark I prototype fuel elements produced chunks of porcelain filled Yankee prototypes. Flow capacities of nozzle plate pulsed columns operated under dilute Purex fiowsheet conditions were determined. Fuel pins made with compacted sol-gel ThO/sub 2/ and U/sup 235/ were irradiated without difficulty to 17,000 Mwd/t. Routine operation of the rotary denitrator to give ThO/sub 2/ product was …

A summary of the progress on development of the ALGOL compiler for the Control Data Corporation 1604 Computer is presented. This computer is based on machine-independent specifications developed at ORNL. A brief description of the structure of the compiler is included along with discussions concerning language restrictions, the hardware language representation, and the required equipment configuration. An example illustrates the generated program instructions. (auth)

8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigate methods of fabricating Pu-Al reference alloy for EBR-I Core IV is described along with the production of fuel rods for this core. The procurement, fabrication, and inspection of components other than Ra material for Core N of EBR-I was continued. Data obtained in nondestructive inspection of EBR-I Core IV components are presented along with data concerning properties of and radiation effects on Al-Pu alloys. EBWR Fabrication Programs. The work in these programs was largely concenned with fabrication of a control-rod-drive assembly made of 17- 4 PH stainless steel. Fabrication of Borax-V Boiling and Superheater Fuel Elements, Control Rod Drive Shafts, and Control Rods. Data are …

Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol% UO/sub 2/ dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO --UO/sub 2/ ceramic fuel materials is described. From the results obtained, it is believed that BeO --UO/sub 2/ fuel materials of the type studied will exhibit satisfactory performance in the Experimental Beryllium Oxide Reactor. (auth)

A summary of activities which took place following an incident at the SL- 1 is presented. No attempt to determine the incident cause is included. A brief description of the SL-1 and the operating program in progress prior to the incident is given along with detailed information on various aspects of the past incident developments. (J.R.D.)

Bar-extrusion tests were performed at 50. 65, and 80% reductions at room temperature and 300 deg C. Tensile tests were conducted on as-extruded and heat-treated specimens. The results are tabulated for comparison. The extrusion of small tubing, 0.560-in. OD x 0.030-in. wall, in the first and second tube- extrusion steps are described. (B.O.G.)

An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)

Thirteen papers are included; separate abstracts have been prepared for each. Abstracts of two papers on some optical and electrical properties of materials and nondestructive testing of reactor irrcdiated metals are also included. These two abstracts are not included in NSA. (N.W.R.)

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A pumped boiling rubidium loop was designed, operated, and analyzed. The loop simulated some of the characteristics of a boiling rubidium space power conversion system. Such a system would involve either a reactor or heat exchanger as the power source, and a turbine and radiator as the power conversion and vapor condensing equipment. This loop was used to study instrumentation and control problems and effects of rubidium corrosion on containment materials, and to gain some rough physical property and heat transfer data on rubidium. The first loop operated with 316 stainless steels and was run for l72 hours at various temperatures, the maximum being 1550 deg F boiling. The 316 stainless steel loop was operated only a short period since it was intended as a system shakedown measure. The second loop was Nb-l Zr loop alloy operated for 455 hours total at l840 deg F and a vapor quality of 9%. ln the latter loop, the last 335 hours of operation were continuous. Stable boiling at this vapor quality level was achieved withont the use of special liquid vapor phase separaration devices. Operation of the loop was stable in all phases; however, overheating of the environmental chamber was observed due …

A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)

Manufacture, assembly, and pararmetric testing of the first 60-watt thermoelectric generator were completed. All of the Sr-90 fuel process equipment was installed. Equipment checkouts and process dry runs have indicated a number of problems. The problems will probably cause a slight delay in hot operation; however, it is expected that schedule commitments in completing the fuel for the SNAP-7B system will be met. The power output of the Coast Guard SNAP-7A system is decreasing much faster than anticipated. A comparison of power output and hot and cold junction temperature readings with parametric operational data shows that the generator is performing as predicted. A plot of the decay in hot junction temperature (cold junction temperature approximately constant) indicates that the isotope fuel had too much Sr-89 and, therefore, too little Sr- 90. Restoration would consist of changing the high conducting inert gas, helium, to a mixture of helium and argon which has better thermal insulating properties. (auth)

An investigation was conducted to determine the performance of a vapor- space feed nozzle which sprayed aluminum nitrate solution on the surface of a fluidized bed calciner. Results indicate that this type of feed system is satisfactory for calcining aqueous wastes from the processing of spent aluminum- type nuclear fueIs. Process and product control were achieved by adjusting the volumetric ratio of the air to the liquid fed to the nozzIe. The results obtained at various operating conditions are compared with those from a pneumatic atomizing nozzle submerged below the surface of the fluidized bed. (auth)

S>Activities included completion of room-temperature extrusion tests on Zircaloy bar, and extrusions with 50% reduction at temperatures up to 400 deg C. Results of these tests are tabulated along with results of billet piercing tests at 300 deg C. It is noted that production of capped Zircaloy tubes by cold extrusion appears promising. (J.R.D.)

Data are tabulated for the characteristic parameters of PuO/sub 2/ powders prepared by the continuous oxalate precipitation process. The results show that the PuO/sub 2/ surface area decreases almost linearly with calcination hold times at 760 deg C. A thermogravimetric study of the decomposition of Pu oxalate indicate the formation of an initial stable compound at ~ l00 deg C and a stable intermediate at ~ 300 deg C. Characteristic data are tabulated for UO/sub 2/ -5% PuO/sub 2/ and UO/sub 2/-20% PuO/sub 2/ powders prepared by coprecipitation. Preliminary blending studies giving a final UO/sub 2/ -0.5% PuO/ sub 2/ powder show that a more homogeneous product is obtained if two powders of the same surface area are used. Results are given for preliminary studies of the direct preparation of high-density coarse particles. A study was made of the simultaneous determination of Pu and U by differential spectrophotometry. Sintering studies were made on PuO/sub 2/ and on both mechanically mixed and coprecipitated PuO/sub 2/UO/sub 2/; the results indicate that the blending and mixing procedures are unsatisfactory. The eutectoid-like microstructure observed in sintered PuO/sub 2/ pellets appear to be Pu/sub 2/O/sub 3/. Preliminary preparations of sintered PuO/sub 2/ spheres coated with …

Work is summarized in the areas of orbit theory, injector studies, ring magnet systems development, vacuum system development, the radio-frequency system, beam extraction, and targetry. (B.O.G.)

The development and fabrication of Pb-Te pellets, contacted to Fe end caps, for use as elements in thermoelectric converters for the SNAP 10A program, is described. The method adopted consists of contacting, by hot pressing in a controlled atmosphere, 24 pellets simultaneously, using q-layer, 8-cavity graphite dies. The optimum hot pressing parameters were found to be 5000 psi at 1550 deg F for 30 min. Several thousand elements were produced by this relatively high-volume process, modifying the normally slow and expensive hot pressing by the use of multilayer, multicavity dies and automatic controls. (auth)

Progress is reported on development of liquid metal and water cooled reactors. Details are included concerning the EBWR, Borax V, ZPR-III, ZPR-VI, AFSR, EBR-I, EBR-II, and FARET. Developments in general reactor technology are reported in applied reactor physics, reactor fuel and components development, heat engineering, and chemical separations. Advanced systems research and development was devoted to the Argonne Advanced Research Reactor and a conduction- cooled reactor to substitute for isotope heat sources. Safety studies are reported on thermal and fast reactors. (J.R.D.)

The 3 kw nuclear auxiliary power unit deslgnated SNAP II is intended for use in a satellite vehicle. The system consists of a reactor heat source, a mercury Rankine engine, and a permanent magnet alternator. The design details, test results, and development of the SNAP lI alternator are presented. (auth)

A review is given of progress in recent years on the problem of calculating the resonance escape probability from the resonance parameters. A computer program (QUERY) for applying the Adler-Hinman-Nordheim method of calculating resonance escape in a lattice is also reviewed and applied to a series of calculations of integrals for U--water, and UO/sub 2/--water systems at various fuel temperntures. The results are compared with those obtained in Monte Carlo calculations for a variety of lattices at room temperature. Monte Carlo calculations at elevated temperatures were also made for comparison. Comparisons were also attempted for resonance escape calculations with experimental measurements of ratios of epithermalto-thermal capture in U in various lattices. Problems involved in making such comparisons when enriched fuel elements are involved are discussed. (J.R.D.)

The reduction and analysis of data from two re-entry heating tests on simulated SNAP fuel cores were completed. lmportant points in the analysis are presented. ldentification of one test specimen gives support to the following significant conclusions - the computational techniques used in re-entry analysis are highly accurate and the design theory applied to the design of SNAP flight hardware for burnup is conservative. Preparations for a third fuel core ablation test were concluded. For this test, data collection and reduction methods were improved through changes in the telemetry canister, the fuel-simulating alkali metals, changes in camera filters, and modification and calibration of test equipment. (auth)

The SNAP 7 program is being conducted for the purpose of developing 4 radioisotope fueled thermoelectric power generation systems. An important phase of this program is the processing of Sr/sup 90/ into heat sources for these systems. The thermoelectric reliability breadboard model and the operating model of the 10-watt thermoelectric generator were assembled and prepared for tests. The SNAP 7B and 7D 60-watt thermoelectric generators were designed, materials were received, and fabrication of components was initiated. Fuel process engineering, nuclear chemistry audit, and manufacturing fuel processing equipment achievements are discussed. (M.C.G.)

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