The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This portion describes the studies of advanced applications of nuclear reactors that were performed, including various types of aircraft, missiles, space vehicles, ships, and portable power plants.

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Design criteria are given for the ORNL High- and Intermediate-Level Liquid Waste Facility. (J.R.D.)

Four zirconium fuel processes -the present STR process, the modified Zirflex process, the barium fluorzirconate process, and the sodium formate process-were evaluated in detail for technical and economic feasibility. The evaluation was based on installation as the second generation ldaho Chemical Processing Plant zirconium process. Two nonaqueous processes, the ARCO and the fused salt fluoride volatility processes, were included in a preliminary evaluation, but were eliminated on the basis that major problems inherent in the processes are not yet solved. A continuous version of the STR process was concluded to be the leading contender for rmmediate plant applicator. (auth)

A philosophy for designing wideband multistage transistor amplifiers is discussed. The amplifier is visualized as an integral unit, the interstage networks constituting the elements of the amplifier unit. By designing the amplifier as a unit and adjusting the over-all response (gain and bandwidth) with the interstage time constants, an increase in gainbandwidth product is realized over the iteratively designed amplifiers. The resulting increase in gain- bandwidth product results from absence of the bandwidth shrinkage factor for multistage amplifiers. Formulas are derived for both a two- and three-transistor integrally designed wideband amplifier, in which shunt peaking networks are used for coupling. Experimental amplifiers were constructed following these formulas, and the observed performance agreed with the calculations. (auth)

MACE is a Monte Carlo code, written for the IBM 7090, to evaluate the efficiency of radiation collimators in terms of the ratio of collided to uncollided flux reaching a target. The analysis can be performed with as many as 30 energy groups. Up to 5 materials (8 elements) may be used in the description of the collimator system. Provisions are included for specification of source particle density and angular distribution functions and for tilt of the source plane with respect to the axis of the collimator. (auth)

Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)

As a means of reducing the quantity of radioactivity released to the environment by radioactive liquid waste discharges at ORNL, it is proposed that two 50,000-gal stainless steel storage tanks and a 600 gph stainless steel, submerged-coil evaporator be installed. The tanks, approximately 10 ft in diameter by 85 ft long, will be equipped with cooling coils attached to their outside surfaces for removal of a maximum of 300,000 Btu/hr of decay heat, and will be supported inside a concrete vauit for containment. The evaporator and a feed tank will be installed inside a cell shielded with 5 ft of concrete and will process mainly intermediate-level waste from the concrete tank farm, but will be able to evaporate high-level waste as well, if required. Two additional cells for the condenser and other off-gas equipment will be housed with the evaporator cell in a building with an operating area and sampling gallery. The capital cost of this installation is estimated to be 226,000. (auth)

Recent developments in the classical theory of fully ionized gases and strong electrolyte solutions are reviewed, and are used to discuss the equation of state at high temperature and low densities. The pressure is calculated using the ring-integral approximation, and quantitative estimates of higher correction terms are given. The effect of short-range repulsive forces is shown by comparing the results with two kinds of potential functions: hard spheres of diameter a, and "soft" spheres for which the short-range potential cancels the Coulomb potential at the origin, and decreases exponentially with distance. It is found that the use of either type of potential extends the range of validity of the ring integral approximation to considerably higher densities and lower temperatures. Since there is little difference in the results for the hard spheres and the soft spheres in this range, the latter is investigated more extensively since it is more easily handled by analytical methods. The expressions derived for the free energy of a system of charged particles can also be used in ionization equilibrium calculations, and the effect of electrostatic interactions on the equilibrium concentrations of various kinds of ions is indicated.

Thorium and uranium carbide nuclear fuel particles were evaluated by metallographic and x-ray diffraction techniques. Techniques were developed to etch the polished surface of Th--U carbide to reveal the grain structure. In addition, techniques to determine particle density and coating thickness were developed. Comparison of the data indicates that the use of spherical particles allowed for more precise determination of the coating thickness, density, and strength of coatings. Strength of individual particles was about 700 to 1300 g per particle. A large scatter in crushing-strength values was observed when individual particles were crushed. Consequently, a relative crushingstrength test was developed for comparing coating strength: loads were applied to a column of particles in stepped increments, and broken coatings were detected by observing a weight gain in moist air from hydrolysis of the Th--U carbides. A correlation of relative crushing strength and coating thickness was obtained. The crystal structure of the C coatings was found to depend on the temperature of deposition in the range from 1400 to 2400 deg C; the twodimensional structure became more defined with increasing deposition temperatures. Subsequent annealing at 2400 deg C of the coatings deposited at 1400 deg C and at 2200 to 2400 deg …

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Progress made in the development of the Experimental Beryllium Oxide Reactor (EBOR) is reported. The objective of the EBOR program is to develop a gas-cooled, beryllium oxide-moderated reactor which can be used in conjunction with a closed-cycle gas turbine or a steam cycle for a small land-based or a maritime power plant. Progress is reported on reactor development, reactor physics, and materials development. (N.W.R.)

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The New Production Reactor, as compared to existing Hanford reactors, employs new and unique design concepts. To properly evaluate these design concepts and their effects on reactor operations, nuclear safety, and reactor life, a comprehensive testing program is planned; this program, with its objectives and restrictions, is discussed in this report. It has been developed along the same line as the C and K Reactors test, programs, and is expected to require a total time of 6--8 weeks of round-the-clock testing. This estimate includes fuel loading time, but does not include time allotments for engineering acceptance tests prior to power operation nor does it include any of the time necessary for engineering and physics tests during the extensive power ascension program. The main body of this report is presented in three parts. The first section describes startup hazards and restrictions, reactor and component safety provisions prior to loading, and the itemized listing of quantities to be measured. The second includes preliminary material and plant conditions and a brief description of the individual tests. The third section (the Appendix), written in procedure language, comprises a rather detailed description of each individual test on a tentative basis; final test details and procedures, …

The specification contains information concerning the material, process, and product requirements to be met by the fabricator. (J.R.D.)

Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-pressing techniques. The densities of these compacts decreased with increasing B content. Compact strengths, however, were noticeably increased with B content of 20 wt%, suggesting that the B acts as a sintering aid. Thermal stability was evaluated by annealing compacts under a variety of temperature and atmospheric conditions. The upper limit of the ioss of 13 was 5% to 10%~ in 200 hr at 2000 deg C--considerably less than would be predicted from the Langmuir evaporation equation. Diffusion of B atoms through the pores of the graphite, rather than evaporation from the surface, was found to be the rate- controlling step in the loss of B. Compacts containing 20, 30, and 40 wt% B were irradiated at 350 and 700 deg C to 1.0 and 2 4 x 10/sup 21/ nvt(fast). Physical integrity of the compacts was good after irradiation. Slight increases in tensile strength were noted in several instances. (auth)

This report explains a mathematical algorithm designed to complete contour descriptions of weapon components which have been only partially specified by free-form data.

The filtrate stream from the precipitation--filtration step of the Button Line process must be recycled to recovery operations to reclaim residual plutonium. Present practice is to transfer the filtrates to Recuplex, concentrate by a factor of 6 to 10, and blend into the feed stream for solvent extraction purification. Limited tankage is available for solution storage. Interruption of Recuplex operations necessitates termination of operations in the precipitation-filtration steps and other Button Line areas. Filtrates can be recycled to one of the parent solvent extraction plants for recovery. However, excessive handling operations are encountered by this processing method. This document describes the anion exchange flow sheets and equipment for processing the filtrate stream without dependence upon other recovery operations.

The economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO/sub 2/ nuclear fuels were compared. A 2.66 metric ton U/day head end portion of a plant was designed for each process and capital and operating costs were developed. For plants of this size and larger, mechanical shear-leach processing has the advantage of ~20% lower capital cost and 50% lower operating cost. Processing costs of stainless steel-jacketed UO/ sub 2/ by the Sulfex and shear-leach methods, including amortization and waste disposal but excluding solvent extraction, were .78 and 7l/kg U, respectively. Storage of stainless steel waste produced by the shear-leach method is less costly by a factor of 20 than for Sulfex. (auth)

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