Data on 13,000 person 15 yr of age or older obtained during detailed clinical examinations, including radiological recorded heart size, were correlated with sex, age, height, and weight of subjects to arrive at a standard heart size for Hiroshima residents This information will be used in investigations cardiovascular disease in the population.

Experimental data supporting lower valence halides of scandium were not found in the literature. Our investigation was of the phase diagram of the ScCl3-Sc system, and also the vapor pressure-composition isotherm (at 960 degree) for this system. Investigation of the ScCl3-Sc system presented particular difficulties in comparison with analogous systems for rare earth elements in that ScCl3 is highly volatile (boiling pt. = 967 degree); according to our data the vapor pressure is 512 mm Hg measured at 960 degree C. Furthermore, ScCl3 and its vapors react vigorously with quartz. Because of the mentioned extent of reaction in a quartz ampule, the inside was covered with a solid layer of metallic molybdenum for use with relatively large batches of ScCl3.

The biological evaluation of the thermal neutron capture reaction of boron-10, B10 (n,α)Li7 + 2.786 MeV, has previously been studied, using different particles from the boron-10 thermal neutron capture reaction compared with 250 kvp x-rays has been reported as 1.05 for spleen-thymic weight reduction (1), as 1.5 to 2.0 for skin lesions in pigs (2), and 1.87 for skin lesions of the rabbit's ear (3). The significance of such a calculation is felt to be unreliable for the boron-10 reaction in animals because of the vagaries of dose determination resulting from irregular boron distribution, and by the presence of an adventitious irradiation from fast neutrons and capture gammas that is inadequately determined at present. Our present experiment attempts to circumvent the difficulties attendent to studies of the boron-10 reaction in animals by comparing the effect of this reaction on the proliferative capacity of HeLa cells with those produced with 250 kvp x-ray.

In these lectures we will discuss some examples of information about magnetic properties of solids which can be obtained by neutron scattering. We consider a scattering process in which a neutron with wave vector k and spin σ is incident upon a solid in state q>. (Here q stands for all of the quantum numbers which describe the state of the solid, such as spin and orbital electronic states, phonon numbers, etc.) After interacting with the solid, the neutron goes off with wave-vector k' and spin σ', leaving the solid in state q'>. In performing an experiment of this sort one does not usually observe the initial and final spin states of the neutron or the initial and final states of the solid. We must then sum over all possible final states and average over all initial states.

We consider the kinetic isotope effect in three center reactions of the type of A+BC→AB+C. Such model calculations are a good approximation to primary hydrogen isotope effects. For abstraction or transfer reactions, B becomes H, D, or T. The dynamics of the three storm system are calculated for a general quadratic potential, with the assumption that the potential energy is constant along the reaction coordinate (flat top barrier). This model system can be calculated in detail and serves to illustrate the relationship between kinetic isotope effect and chemical bonding in the transition state. The statistical mechanical part of the calculation can be carried out exactly within the framework transition state theory or in any one of a number of approximations. The γ bar method gives particularly good insight into the chemistry of the problem with a minimum of arithmetic.

Optical absorption and photoconductivity measurements have been made on single crystals of pure synthetic rutile (TiO2). Reactor irradiations at 70°C totaling 4.8 x 10 18 nvt fast and 1.69 x10 19 nvt slow did not produce any discernible optical absorption bands; however, the transmission decreased 5 percent at all wavelengths. Reactor irradiation induced a [illegible] five photoconduction peaks in the wavelength range 4200 to 14,000 A. In addition the photopeak at 4065 A (3.05 eV) was enhanced and there were drastic changes in the dependence of photocurrent with light intensity. Gamma-ray irradiations as large as 10 9 r do not change the conduction properties. The photocurrent is proportional to a power of the light intensity; the power range from 0.65 to 1.24, for the crystals described in this work. The photocurrent vs. voltage dependence is more complex.

The present core of the Brookhaven Graphite Reactor consists of some 4900 highly enriched uranium fuel loaded in 615 horizontal fuel channels passing through a 25 foot cube of graphite moderator and reflector. The core is divided into two halves (north and south) by an 8 cm. wide vertical gap in the center of the graphite. The cooling air enters the reactor through inlet filters, at the rate of 270,000 CFM, passes into the central gap and flows bi-directionally through the north and south halves of the core. It then enters the collecting plenums and flows into the north and south ducts. The air is first monitored by the north and south exit air monitors located within the pile building. These are moving filter tape monitors with beta scintillation detectors. They are essentially operational monitors and are maintained by reactor operations. They are essentially operational monitors and are maintained by a reactor operations. The air then passes through the exit air filters, heat exchanger, venturi and on to the fan house where the north and south ducts join. After the fan house the air is monitored by Argon-41 by a Kanne ion chamber syste.

Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a range in tissue of about 8-14μ or approximately 1 cell diameter (1). This fact and the reported favorable partition of boron between tumor and the normal brain suggested a possible therapeutic usefulness which has been investigated clinically. The object of our study is to document the biological effects of the B10 (n,α) Li7 reaction on the brain of dogs injected with boron-10 30 minutes prior to irradiation with thermal neutrons. For this, we felt it desirable to estimate a dose for the boron-10 reaction which if exceeded, produces destruction of normal tissue. This dose could then be a reference dose to be utilized as a maximal limit for the irradiation of normal tissue. We have assured that the largest fluence …

There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression for some physical quantities such as film heat transfer coefficients entering as major parameters the process equation.

The purpose of this report is to determine the amount of refrigeration capacity required to cool down the 80" bubble chamber from ambient temperature to liquid hydrogen temperature.

The undercarriage system is required for translating, rotating, and lifting the 450 ton magnet and bubble chamber assemblies so that it can be accurately positioned in the experimental proton beam of the synchrotron. The system must make provision for the two magnet sections to be separated for the purpose of adjustment and maintenance of internal components.

The following general description of the theory and operation of a bubble chamber is presented so that firms who are interested in fabricating components for the Brookhaven 80" chamber will have a better understanding of the design parameters associated with it. This understanding, coupled with the fabricator's knowledge of manufacturing techniques, should enable the fabricators to suggest solutions to manufacturing problems consistent with requirements for chamber operation. In an effort to increase knowledge of fundamental nuclear particles and their interactions at high energies, various types of detecting equipment have been developed. One of these detectors recently developed is the bubble chamber. While there are variations as to liquids used, expansion techniques, means of illumination, etc. the basic concepts upon which all bubble chambers operate are similar. Therefore, it will be sufficient in this report to consider only one specific type, that is a chamber using liquid hydrogen

Satisfactory dense crack—free dispersions of spheroidal UO2 — ThO2 particles in BeO can be produced by "co-sintering", a process in which unsintered particles are hydrostatically pressed in BeO and the dispersion is sintered in one step, the large voids and cracks in dispersions of fully sintered particles in BeO following sintering are related to mismatched sintering shrinkage between the two phases; they are probably indicative of a high interfacial energy between the two phases. Co—sintering has been used for individual fabrication of specimens for irradiation testing, but is not immediately applicable to large scale fabrication of fuel element shapes, Possible modifications of the method are discussed.

"Properly designed and fitted respirators have been effective devices for reducing the inhalation of toxic aerosols. The degree of protection afforded by these devices has not been quantitatively measured under actual work conditions except by bioassay or other elaborate techniques. This report describes a new quantitative technique for evaluating over-all respiratory performance under conditions comparable to exposure to highly toxic radioactive materials such as plutonium and non-radioactive materials such as beryllium."

" A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to which the encapsulated gases and particles can diffuse and be removed."

Abstract: A potentiometric study of the complex formation between citric acid (H3L) and the uranyl ion at 25° and ionic strengths of 0.1 and 1.0 (KNO3) is reported From the concentration dependence of the formation constant, it is concluded that polynuclear complexes are formed in which bridging between metal ions occurs through carboxylate and hyroxyl groups of the ligand. The values of the logarithms of the formation constant of the metal checlate [UO2L-]/[UO2+][L3-] and of the dimerization constant [(UO2)xL22-]/[UO2+][L3-] are found to be 7.40 and 4.07 respectively. Infrared absorption measurements of protonated and dissociated carboxyl groups in aqueous uranyl citrte system indicated the presence of both carobxy-late and hydroxide bridging in the polynuclear complex. On the basis of the "core plus links" treatment of polynuclear complexes, the polymeric species in solution in the buffer region between 3 and 4 2/3 moles of base per mole of metal complex appears to be predominantly (U)2)2L2((OH)5(UO2)2L2)216-.

First paragraph of report: M. Neumann and H. Sherrard reported the development of a wire spark chamber experiment toward receiving digitized spark information. Since late 1962 our effort has been directed toward a wire-chamber with a core memory, using standard ferrite cores, and toward an on-line operation between spark chamber and computer.

Technical report. From Abstract : "A number of the physical properties from which we can obtain both direct and indirect information concerning the band structures of metals, have been measured for most of the rare earth metals. It was thought that it would be desirable to review ans examine these data and try to tie them together. For this purpose the very low and room temperature heat capacities, Hall coefficients, magnetic susceptibilities, spectral data and electrical resistivities were examined."

Technical report. From Introduction : "In a recent study by Spedding, et al. on some rare earth alloy systems, an intermediate phase was found to form when a light rare earth (ABAC stacking) was alloyed with a heavy rare earth (ABAC stacking). This intermediate phase was found to have the structure of samarium metal with the stacking ABABCBCAC and was designated "delta". Since the cause of this rather unusual structure occurring in either samarium metal or these alloys is not known the study of these phases as some of their properties is continuing in the Ames Laboratory. It was the purpose of the present study to extend our knowledge of the composition and more of formation of these phases."

Technical report. From Introduction : "The nuclear volume dependent isotope shift of optical spectral lines has long been a very useful means for studying the changes in the nuclear size or shape for different isotopes of heavy elements."

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Project fuel fins irradiated to 1860, 3000, and 5300 MWD/T have been successfully sampled in the Radioactive Materials Laboratory. The samples have been dissolved and aliquots delivered to Chemistry for Mass Spectrometry and burnup determination. The first Stanford Pool Irradiation indicated that there was some inconsistency in the thermal flux and the near thermal epithermal flux. The experiment was repeated, increasing the number of foil wheel positions from two to three. The data from the second measurement are being reduced. The EPITHERMOS code modification has been completed. Comparisons between the results computed by the code and experimental data show much improved agreement. The metallographic photomicrographs of a polished half-pellet from rod F, irradiated to 5000 MWD/T, show structure very similar to that shown by the pellet from rod S, irradiated to 1860 MWD/T.

Abstract: A materials exposure program has been established in the Garigliano Nuclear Power Plant to measure the effect of neutron irradiation and time at temperate on the mechanical properties of the reactor pressure vessel steel. Base metal specimens were made from portions of the pressure vessel steel, and weld heat-affected zone and weld metal samples were taken from a weldment made from the pressure vessel steel and simulating a pressure vessel circumferential weld since there are no longitudinal welds in the forged ring shell. The specimens were sealed in helium-filled capsules and placed in the reactor vessel at locations where they will be exposed to a variety of conditions. Tensile property changes will be measured by pre- and post-irradiation tests on small tensile specimens. Fracture characteristic changes will be measured in similar fashion by Charpy V-notch impact tests. The program is planned to cover a 32-year period, with specimens to be removed for test at intervals of 1, 2, 4, 8, 16, and 32 years.

Technical report describing a UO2-Mo cermet fuel assembly fabricated for long-term irradiation performance testing in the Vallecitos Boiling water Reactor. The design and fabrication histories of this assembly are described and pre-irradiation data on each individual rod are presented. Molybdenum was added to improve the bulk thermal conductivity of the fuel, so that fuel temperatures would remain comparatively low during high-power level operation of the fuel element. The molybdenum was incorporated into the compacts either as fibers or as a thin coating on individual UO2 particles. Fuel pellets were produced from these materials by vacuum hot pressing. The distribution of the molybdenum in both types of cermet fuels appeared favorable to good heat transfer. The fibers were oriented predominantly in the radial planes of the pellet as a result of the uni-directional compaction during the hot-pressing operation. In the pellets made from the coated particles, a continuous network of molybdenum occurred as a result of the coating welding together during the hot-pressing operation. The test assembly contains eight fuel rods; three contain UO2-Mo cermet, three contain the cermet produced from the coated particles, and two are for reference and contain the conventional sintered UO2 pellet fuel. The nominal outside diameter …

Technical report describing how corrosion data and exposure effects were obtained by subjecting metallic samples, during programmed test runs to flowing sodium in 6 test loops fabricated with various combinations of three selected materials, Type 316 stainless steel, 2 1/4 Cr-1 Mo alloy steel, and 5 Cr-1/2 Mo-1/2 Ti alloy steel. Information produced by each test run, including operational and metallurgical data and analyses, is presented. Data are shown in tables, graphs, and drawings.