Surface contamination with beryllium becomes a hazard to health only when the potential exists for resuspension in air in enough quantity and for enough time to exceed the prescribed standards for airborne exposures. There are several factors governing the rate and nature of resuspension phenomena. These factors include: the quantity and properties of the particular beryllium compound causing the contamination, the nature of the surface, activities in the vicinity, ventilation in the area which might affect the dilution of resuspended particles, and the presence of other control measures such as respiratory protection and use of wet methods. Generally, it has been found that the problem is minimal and can be easily controlled by exercising good judgement based upon consideration of pertinent factors governing resuspension, and a knowledge of the nature of beryllium toxicity.

The Chapman-Jouguet pressure and equation of state of the high explosives PBX 9404 and LX04-01 have been experimentally derived. To assure a strictly one-dimensional geometry, spheres of high explosives were used. Experimental measurements of the radius-time history of material accelerated by the explosive gases were used in conjunction with finite difference calculations of the hydrodynamic equations to obtain some previous inaccessible data on high explosives.

The angle errors of a rotary table can be accurately measured by stepping off the angles with an optical caliper and computing table error from (1) the error readings at each angle measured and (2) the cumulative caliper error that will be evident when the circle is closed at 360', eliminating the necessity of adjusting the caliper to the exact setting.

When the Brookhaven AGS started operation in the summer of 1960 very little experience with targeting in strong focusing proton synchrotrons was available. While it was evident that targeting techniques would differ markedly from those used in weak focusing machines, only actual running experience would set the proper parameters for a truly satisfactory targeting system. It was, therefore, an advantage that temporary targeting devices were used initially. Work on a more permanent system was not started until the summer of 1961, and the first component of the system installed in January 1962. While further refinements are still continuing the essential features of this targeting system have now sufficiently proven themselves in actual operation to remain unchanged. This system in its present form is the subject of the first portion of this paper.

The BNL cold neutron facility has been used to obtain inelastic scattering cross section data from three first-row transition elements, titanium, vanadium, and nickel, and a random binary alloy Ti.67-Zr.33. From the data, we have computed vibrational frequency distributions exhibit peaks corresponding to major critical points. A comparison of the distributions from the different samples leads to the following conclusions: 1) The shape of the frequency distributions of the b.c.c. metal (V) and f.c.c. metal (Ni) are remarkably similar, the relative positions of the critical points being the same for both; 2) The frequency distribution of the h.c.p. metal (Ti), which has two atoms per primitive cell, shows structure corresponding to acoustical and "optical" modes of vibration; 3) The titanium-zirconium alloy has the h.c.p. structure, and its experimental frequency distribution is similar to that of titanium, except at low frequencies where alloying with the heavier mass zirconium atoms tends to smear out the peaks corresponding to acoustical modes. Measured frequency distributions were obtained for the titanium-zirconium alloy slightly above and below the critical temperature for the phase transition to b.c.c. structure. The frequency distributions in the two phases are different, the most striking feature being a shift of the high …

The subject of this paper is the experimental and technical aspects of the measurements of nuclear resonance parameters. I will confine my remarks to those reactions induced by low energy neutrons, i.e. neutrons of less than approximately 100 kilovolts. The bulk of these measurements have been performed by neutron time-of-flight techniques, and I will direct my attention to these techniques. The first half of this discussion will concern the apparatus with which these measurements are made; the second part will be a discussion of the various experiments by which these parameters are measured, with an emphasis in both areas of discussion on relatively recent developments in the field.

Technical report. From Abstract : "Thermal, metallographic, and vapor pressure data were obtained to establish the phase boundaries and the standard free energy, enthalpy, and entropy of formation for the compounds in the yttrium-zinc system."

From abstract: "Distillation procedures used for purifying yttrium metal, producing metal containing less than 150 ppm oxygen and lower concentrations of most of the other common impurities, are discussed. Some of the physical and mechanical properties of the distilled yttrium indicate: (1) a melting point of 1510°C, (2) a solid state transformation at 1459°C obtained from high temperature resistivity data, (3) a Rockwell H hardness of 60 and (4) improved rolling and swagging characteristics."

This report contains a listing of the bound-proton kernels for neutron scattering which were calculated in conjunction with the USAEC Control Rod Materials Program.

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.

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

From abstract: "The phase diagram of the thorium-molybdenum alloy system has been determined to be the eutectic type with a eutectoid reaction associated with the thorium alpha-beta transformation. X-ray, thermal, electrical resistance and metallographic methods have established the eutectic point at 1380 ± 10°C and 7.0 ± 0.5 wt % molybdenum. A eutectoid reaction is proposed at 1358 ± 5°C and less than 0.1 wt % molybdenum. No solubility of thorium in molybdenum was detected at 1325°C."

Measurements of the interfacial tension between water and tributyl phosphate solutions were made for application to the analysis of Marengoni effect in solvent extraction. A 24 hr flame calcination run to product Th02 particles yielded 40% as product and 54% collected from the furnace walls and from a coarse particle trap. The elution rates of uranyl ion from Dowex 21K using sodium nitrate could be approximated by assuming apparent diffusion coefficients of 1.67 x 10^-7 and 1.18 x 10 ^-7 cm^2/sec, respectively for 960µ and 820µ resn while the corresponding apparent coefficients using sodium chloride were 1. 78 x 10^-7 and 1.27 x 1-^-7 cm^2/sec. The reacting surface of ThO2 Universal Match Co. pellets was determined as a function of fraction dissolved. The lead scews and companion nuts from both the multipurpose saw and dejacketing machine were coated with a baked on lubricant. In Zirflex decladding studies using 4.5 M NH4F - 0.5 M NH4NO3, the average dissolution rate of Zircaloy-2 was decreased only 10% when the overhead condensate was withdrawn and 1.0 M NH4OH was added to maintain the volume.

Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.

The feasibility of improving the mechanical properties at 1700-1800°F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion has been explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion characteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispersion with an interparticle spacing of about 2-3 µ. High-temperature native oxides of the Fe-Al-Cr alloy consist largely of Al2O3 and in theory would serve as a satisfactory second phase.

It is proposed in this report to describe a new two-phase flow mixing length model. It consists of treating the two-phase system as a continuous medium and applying to it the methods and assumptions so widely accepted in single-phase turbulent flow. Because it reduces a two-phase problem to an equivalent one in single-phase flow, the proposed model can be readily used to predict the effects of flow rate, channel geometry, and channel direction in two-phase flow.

"Dust and gas masks and respirators have been an effective method under certain environmental conditions to reduce the inhalation of toxic aerosols. Under many conditions, however, their efficacy has been seriously questioned. It is the purpose of this study to evaluation over-all respirator performance on fine aerosols and to develop equipment whereby a greater degree of respiratory protection may be assured with reliability for highly toxic atmospheres."

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.

A brief series of experiments was performed to study the high temperature reaction of the Zircaloy-uranium-aluminum system at the request of Reactor Engineering Operation, Irradiation Processing Department. Knowledge of the high temperature behavior of this combination of materials is important to the evaluation of reactor behavior during possible accidental over-heating of a fuel channel.

Abstract: "The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum-35 w/o uranium were investigated. Initial investigations were concerned with the effects of 3 w/o ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 w/o level, additions of germanium, silicon, tin or zirconium inhibited the formation of UAl4 and thereby increased the content of the aluminum matrix in the alloy. It was also noted that these additions decreased the pressures required for extruding, and the tin addition also improved the homogeneity of cast shapes. Lead and palladium also improved the homogeneity of the cast material; however, neither of these was an effective inhibitor of UAl4 and free lead was detected in the alloy to which lead had been added at the ternary. From these studies it appears that tin and zirconium are as effective as silicon in enhancing the fabricating characteristics of aluminum-35 w/o uranium alloys, and may prove superior when evaluated on the bases of casting qualities and recycling characteristics."

From Abstract: "A literature survey was made of both welding and brazing methods that might be used to minimize the amount of exposed core material and provide the longest path for corrosion in the event of a defective weld in enextruded Zircaloy-2-clad uranium and uranium-2 w/o zirconium fuel elements."

A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.

Report discussing a system designed to "punch binary data from an RCL pulse-height analyzer (PHA) on paper tape concurrent with the printing of decimal information."

The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding soil.