This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.

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.

None

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor and other facilities to improve the technological limits of boiling water reactors in several areas. Progress is reported here.

"A linearized three component MHD theory is given. The three components are two oppositely charged species and a neutral species. Linearized macroscopic equations are presented which in the limit of vanishing magnet field reduce to fluid dynamical equations, and in the limit of vanishing neutral components is frictional. In addition the sound speed that enters is a function of three equilibrium densities. These equations yield a dispersion relation which is tenth order in the wave speed. The decay frequencies of all ten modes are calculated to first order terms in the friction, and are found to be all isotropic."

This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the third quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), and loop operations are included.

None

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)

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.

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)

Presented herein is a philosophy for designing wideband multistage transistor amplifiers. 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 overall response (gain and bandwidth) with the interstage time constants, an increase in gain-bandwidth 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 quite well with the calculations.

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)

Report discussing a studies regarding "imaging qualities and the thermal neutron and gamma-ray sensitivities of several neutron imaging detectors".

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 …

None

This technical report seeks to ascertain which amine species cause the synergistic effect exerted by tri-n-octylamine (TNOA) on the solvent extraction of thorium by TTA, the nature of the species formed, and the values of the equilibrium constants involved. This report also includes 2 figures and 2 tables to accompany the findings.

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.)

None

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, …