The longitudinal electromagnetic interaction of an intense coasting beam with itself, including the effect of a resistive vacuum tank, is investigated theoretically. It is shown that even in the range where the particle frequency is an increasing function of particle energy, the beam can be longitudinally unstable due to the resistivity of the vacuum tank walls. In the absence of frequency spread in the unperturbed beam the beam is shown to be always unstable against longitudinal bunching with a growth rate which depends upon (N/{sigma}){sup 1/2}, where N is the number of particles in the beam and {sigma} is the conductivity of the surface material. By means of the Vlasov equation, a criterion for stability of the beam is obtained; and shown in the limit of high-conductivity walls to involve the frequency spread in the unperturbed beam, the number of particles N, the beam energy, geometrical properties of the accelerator, but not the conductivity {sigma}. A numerical example is presented which indicates that certain observations of beam behavior in the MURA 40 MeV electron accelerator may be related to the phenomena investigated here.

This report covers the following titles: (1) Fertility and litter size of normally ovulated and artificially ovulated mice; (2) Further studies on sterility produced in male mice by deuterium oxide; (3) Planarian disaggregation; (4) Uptake of organic compounds by planarians. II; (5) Effects of environmental complexity and training on acetylcholinesterase and cholinesterase activity in rat brain; (6) Effects of environmental complexity and training on brain chemistry and anatomy among mature rats; (7) Improvements in paper chromatographic techniques for labeled cell extracts; (8) measurement and adjustment of pH in small volumes of solutions; (9) Carbon-14 and Nitrogen-15 tracer studies of amino acid synthesis during photosynthesis by Chlorella Pyrenoidosa; (10) Photosynthesis of {sup 14}C-labeled protein from {sup 14}CO{sub 2} by Chlorella; (11) Further studies on carboxydismutase; (12) Electron microscopy of chlorophyll a crystals; (13) The possible role of chromanyl phosphates in oxidative and photosynthetic phosphorylation; (14) Oxidation-reductions of some coenzymes; (15) Preparation of some [{sup 14}C] labeled substances: glucose-6-phosphate, fructose-6-phosphate, 6-phosphogluconic acid, pyruvic acid, and succinic acid; (16) attempt to synthesize high molecular weight polynucleotides using Schramm's purely chemical method; and (17) Optical properties of some dye-polyanion complexes.

Pumping specifications are given for the B, C, D, and DR reactors at Hanford in August 1963. The maximum capacity is given for equipment in use and equipment that could be used.

This invention discloses a method of making a synthetic nuclear fuel by mixing pure U-233 with U-238 fuels, such as depleted uranium, to produce a fuel that combines the most desirable nuclear properties of both the U-233 and U-238 fertile material. The process requires that U-233 be manufactured in such a manner as to be relatively uncontaminated from U-232. The subject of this invention is a method of fuel handling that incorporates the desirable features of both U-233 and U-238. It is proposed that U-233 be formed by short-term irradiations of thorium that will minimize contamination by U-232. At the end of a short thorium irradiation the U-233 is removed and combined with U-238. This combination then makes a synthetic fuel that has all the advantages of each ingredient but does not run into significant U-232 contaminant problems.

A concentrated study of the present manufacturing process was initiated in the Process Engineering Unit, the purpose of the study being to optimize the present operations, procedures, and methods of the AlSi canning process. It is the purpose of this document to report the findings and accomplishments for that portion of the study concerned with the optimization of component preparation and fabrication within the canning furnace. To date, this study has consisted mainly of heating rate studies of the various components used in the fuel element fabrication with some work being done on the optimization of the heating cycle for these components. This work necessarily serves as the basis for further optimization study.

This report details Hanford Production Reactors operating limits and performance and operating restrictions.

The purpose of this letter is to outline the immediate and long-range plans for increasing the H Reactor coolant flow. The flow can be increased, immediately from the present base of about 84,000 gpm to about 88,000 gpm via the following changes: routine purges; use of non-bumpered fuel; increasing the flow through Fringe enrichment and Fringe Poison tubes by changing orifices; and reaming damaged rear fittings to their original size. The flow can be increased to about 94,000 gpm via the following changes: installing larger Venturis throughout the reactor; reaming rear fittings to a larger size; installing rear nozzles that permit higher tube flows; charging I&E Poison elements in Fringe tubes; and some changes in the water pumping facilities may be necessary.

An important parameter which is required in the study of short-term reactor transients is the prompt neutron lifetime. This document presents calculated values for the prompt neutron lifetime in the Hanford IPD lattices under a variety of conditions. The calculated values for the prompt neutron lifetimes in the various Hanford IPD lattices are shown. None of the values shown include any contribution from the neutron slowing down time. Two different values (1{sub o1} and 1{sub o2}) are presented for each lattice spacing and condition studied. This arises from an uncertainty about the correct definition of the thermal neutron lifetime. Generally speaking, it is conservative, from a hazards analysis standpoint, to use the shorter values. This has been done in all of the kinetics studies concerning the production reactors at Hanford during the last several years. A precise definition and more complete discussion of the values presented are given later in this report.

Dissolver solution samples were analyzed for neptunium, and the data are plotted as g Np/t U vs g Pu/t U.

The problem of designing storage containers for heat-generating fission products or radioactive wastes is complicated by the interdependence of a number of variables. The permissible maximum surface temperatures and internal temperature; the concentration, age, and type of isotope; the thermal conductivity of the materials, the ambient temperatures, the configuration (annular or cylindrical) of the container; and the mechanism of heat removal, all affect the design of the container 4-n that they affect the permissible size. Existing programs for resolving the interrelationships among the variables in problems of this type, while adaptable to almost any geometry in one, two, or three dimensions, have the disadvantage that considerable time must be spent preparing input data for each different size or configuration to be solved. A program was needed which would accept data in engineering terms and permit the solution for many different container sizes with a minimum of input conditioning. The SIZCAN Code described in this report, meets this need by limiting the problem to two different configurations and considering only one dimensional, steady state, heat flow. It can be used to ``zero in`` on geometries to be examined by more rigorous techniques.

Since transducers used in rocket engine applications measure time varying quantities, the characteristics which define the behavior of a transducer under dynamic conditions are extremely important in their applications by the design engineer. Proper calibration of transducers in the dynamic or frequency domain required a thorough understanding of the dynamic or frequency domain required a thorough understanding of the dynamic characteristics of a transducer. Analytical models are generated in his report, and the techniques based on these models for determining frequency response are discussed.

None

BS>The average energy required to form an ion pair, W, when alpha particles are absorbed in mixtures of argon with other gases is studied. The other gases were selected on the basis of their ionization potentials. One group consists of representative gases that have ionization potentials below that of Ar (15.77 ev) and above the doublet metastable state of Ar (11.49 and 11.66 ev). This list includes methane, carbon dioxide, nitrous oxide, xenon, and krypton. The other group of special interest consists of some gases with ionization potentials below the metastable state of Ar. All gases tested in these two groups cause an increase in ionization, i e., a decrease in W, when added to argon. As an illustration of this effect, the addition of 1/2% of acetylene to Ar will increase the ionization by 23% The experimental data, i.e., W as a function of relative concentration of the two gases, were fitted to a model in which it is assumed that energy is transferred from two excited levels in argon to the additive gases in collision processes. Good agreement between the experimental data and calculations based on the model is taken as additional evidence that the excited state notion …

Using the straight-ahead approximation, nucleon-meson cascade calculations have been carried out for a typical proton flare spectrum incident on a shield and for approximately monoenergetic incident proton beams. The shield material considered has approximately the properties of Al. The results from the monoenergetic beams may be used to obtain shielding information for any incident proton spectrum. (auth)

Progress in solid state physics is reported in the following areas: theory, crystals, metals and nonmetals, radiation effects, and other subjects. Separate abstracts were prepared for the fifteen sections of the report. A list of 70 papers and publications is included. (D.C.W.)

The Zirflex and Sulfex processes for chemical decladding Zircaloy or stainless-steel-clad UO/sub 2/ power reactor fuels were successfully demonstrated at irradiation levels as high as 28,200 Mwd/t. The Zircaloy jackets were dissolved in boiling 6 M NH/sub 4/F-- 1 M NH/sub 4/NO/sub 3/, and the stainless steel jackets were dissolved in refluxing 4 M H/sub 2/SO/sub 4/. Both processes gave average soluble losses of uranium and plutonium to the decladding reagents of about 0.05%. Centrifugation or filtration of the highly radioactive decladding waste solutions was required to recover UO/sub 2/ fines produced by fracture of the UO/sub 2/. The fines were recycled and dissolved with the UO/sub 2/ cores in boiling 4 M HNO/sub 3/ solution. About 5 to 6 hr were required for complete dissolution of the UO/sub 2/ core to produce terminal concentrations of 100 g of uranium per liter and 3 M HNO/sub 3/. The core solution was a suitable solvent extraction feed after clarification and adjustment of plutonium valence with sodium nitrite. One cycle of the modified Purex process, in Mini mixersettlers, using 100-g-uranium-per-liter feed solutions, gave losses of uranium and plutonium to the raffinate of less than 0.1%, and gross gamma decontamination factors of about …

Samples of five nuclear-grade graphites were irradiated under constant compressive stresses of 150 and 300 psi. Length changes of the stressed samples are compared with length changes of unstressed control samples, irradiated in the same assembly. Results obtained at 825 deg C and for exposures up to 6500 Mwd/ at. in a Hanford irradiation facility are presented. Additional data on one nuclear-grade graphite, irradiated under 100 psi constant tensile stress, are included. (auth)

Experimental data on nonelastic reactions of protons, neutrons, pi /sup +/, and pi /sup -/ with complex nuclei at incident energies of 20 Mev to 33 Bev were surveyed. The material is grouped according to the incident particle in the above order. Information on the measured quantity, experimental arrangemert, and the experimental error is included. The 200 publications used in the survey, most of them abstracted for Physics Abstracts, are listed. (D.C.W.)

Values of the distance of closest approach, the centerof-mass scattering angle, and the time integral are tabulated as functions of the impact parameter and the relative kinetic energy for each of three repulsive potentials. The classical theory of scattering was used as the basis for the calculations. The potentials used are the Born-Mayer (exponential), the Bohr (exponentially screened Coulomb), and the Thomas-Fermi. (auth)

Progress is reported on the development of gas-cooled reactors. The report contains eleven sections which are abstracted separately in NSA. These sections are contained in two parts: investigations in support of the Experimental Gas-Cooled Reactor and advanced reactor design and development. The four sections abstracted under Part I are: performance analyses, component development and testing, materials development, and irradiation testing of components and materials. The remaining sections are under Part II and they are: development of fueled-graphite bodies, investigations of fueled-graphite systems, clad fuel development, investigations of moderator materials, studies of advanced systems, experimental investigations of heat transfer and fluid flow, and facilities and equipment. (N.W.R.)

An analytical approach and an IBM machine code were prepared for the design of gas-cooled reactor once-through steam generators for both axial-flow and cross-flow tube matrices. The codes were applied to investigate the effects of steam generator configuration, tube diameter, extended surface, type of cooling gas, steam and gas temperature and pressure conditions, and the pumping power-to-heat removal ratio on the size, weight, and cost of steam generators. The results indicate that the least expensive and most promising unit for high- temperature high-pressure gascooled reactor plants employs axial-gas flow over 0.5-in.dia bare U-tubes arranged with their axes parallel to that of the shell. The proposed design is readily adaptable to the installation of a reheater and is suited to conventional fabrication techniques. Charts are presented to facilitate tlie design of both axial-flow and cross-flow steam generators for gas- cooled reactor applications. (auth)

The Special Power Excursion Reactor Test II (Spert II) reactor is a pressurized-water research reactor for conducting reactor kinetic behavior and safety investigations. The facility incorporates sufficient flexibility to permit studies on a variety of cores using a variety of reflectors, especially heavy water. It is designed for operations up to pressures of 375 psig and temperatures of 400 deg F with flow rates up to 20,000 gpm. The engineering features of the reactor and supporting process equipment are described. (auth)

Upon completion of the initial visual examination and dimensional check, the resistors were weighed and the weights were recorded. The measurement of insulation resistance, performed with a megohmmeter, indicated infinity for each resistor. The dielectric strength test was performed with a high potential a-c dielectric strength tester. The test voltage was applied with no evidence of leakage or breakdown in any case. A wheatstone bridge was used to measure the d- c resistance of each resistor. All the resistors were well within their specified tolerance. The resistance-temperature characteristic test was performed in a temperature chamber at --67 to 302 c- F. The resistance of each was measured with a wheatstone bridge at 9 temperatures. The resistors exhibited a negative temperature coefficient, but remained within allowable tolerances. Upon completion of vibration and shock, the d-c resistance, dielectric strength, and insulation resistance, each resistor was measured. There was no evidence of damage in any case. (auth)

Continuous dissolution of 2% U-- Zr alloy fuel in a laboratory-scale Ti dissolver was demonstrated using refluxing 3 M HNO/sub 3/--1.2 M HF--0.4 M HBF/ sub 4/--0.6 M Cr(III)0.4 M Cr(VI)--0.46 M Zr as the dissolvent. Dissolution rates and solution corrosion rates were 8 to 16 mg/cm/sup 2/min and approximates 1 mil/month, respectively. Reagent was added to the dissolver at the rate needed to maintain the potential measured by a Au vs. calomel electrode in the product effluent as close to a preselected standard value as possible. (auth)