Possible experiments that could be performed at the Brookhaven alternating gradient synchrotron using highenergy deuterons and heavier nuclei are reviewed. Particular attention is given to production of high-energy neutrons by stripping. A brief analysis of changes needed to accelerate heavier nuclei reveals such modifications would not be prohibitive. (D.C.W.)

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A total of twenty papers and one roundtable discussion were presented. Separate abstracts were prepared for eighteen of the papers. The papers for which no abstracts were prepared are concerned with impact energy sorption by large shipping casks, design of a Pu and enriched U shipping container, and the roundtable discussion on regulatory standards. (J.R.D.)

An analysis of the dynamics of a check valve disc under the influence of a flow transient is presented. The impact velocities of the disc and the pressure surge resulting from extinguishing a fluid velocity are predicted. This analysis develops the equations of motion of a simple swing disc check valve from Newton's Second Law. Modifications of the analysis necessary for application to other types of valves are described. The developed equations are progiammed for the Philco-2000 digital computer in FORTRAN as the SLAM Code. The Code input consists of the characteristics of the valve and the flow transient. The output of the code includes the dynamics of the valve disc as a function of time and the pressure surge induced by valve closure. (H.G.G.)

The results of a study of the installation and operational characteristics of a SNAP reactor system integrated with a manned space station are presented. The reference system selected was an 11 kw(e) version of a SNAP 2 system employing multiple power conversion units coupled to a single reactor source. Of prime importance is the reactor radiation shield required for the manned system and the use of design features which minimize the shield weight. The weight of the radiation shield is highly dependent upon the geometrical configuration of the space station and the reactor since shadow'' shielding of the manned compartments is required for minimum weight systems. The installation and shielding requirements of the 11 kw(e) system were considered for two types of space station configurations; one was a 10 ft dia cylindrical station with a reactor separation distance of 50 ft and the other a 150 ft dia toroidal station with the reactor located in the hub. The weight of the power system installed in the cylindrical space station was about 9000 lb of which 6000 lb was required for shielding. The weight of the system for a toroidal station was approximates 25,000 lbs of which 20,000 lbs was required …

Calculations are reported relating to the uniform lattice critical experiments performed in the ZPR-VII critical assembly with both THUD and Babcock and Wilcox thoriaurania fuel and heavy water as moderator. Constants appearing in the criticality equation and material bucklings are computed for lattice pitches used. Reflector savings are calcuiated and used in conjunction with experimental critical dimensions to calcuiate geometric bucklings. Analyses are carried out for various experiments, such as measurements of U/sup 235/ and Th-- Cd ratios, water worth, and fuel-substitution experiments. Theoretical and experimental values are compared whenever possible. (auth)

Complete parition functions for non-rigid rotators are obtained for the linear, spherical top, and symmetric top cases, From these are derived expression giving the corrections to the thermodynamic functions due to centrifugal distortion as functions of the rotational distortion constants D. Numerical examples are given for HCN, methane, and ammonia.

This report, from the Chemical Processing Department at HAPO for November 1962, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and weapons manufacturing operation.

Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 times the flow sheet rate did not inhibit the oxidation of the uranium at this temperature. Batchwise mixing in air of dissolver product solution with complexer solution oxidized the uranium within two minutes at 23 deg C or higher. Further studies of continuous zirconium dissolution indicated that precipitation of uranium at the acid inlet can be a problem, probably because of local concentration gradients of free HF, which result in conditions of low uranium solubility. Control of dissolver acid composition by electrical conductance measurement appeared possible due to the linear relationship of conductance with acid concentration. Aluminum alloy dissolution rates in nitric acid were found to vary significantly, depending on the type and amount of alloying agent. Silicon, nickel, and copper in the alloy significantly decreased the dissolution rate. Batch dissolution …

BS>A total of nine sections are included in the report. Separate abstracts were prepared for each section. (J.R.D.)

A calculation to determine the effectiveness of collimators in a high- energy electron beam is described. Numerical results for a 5-Bev electron beam incident on a 135.42-cm-thick aluminum collimator with an inside radius of 0.85 cm are reported. (auth)

Comparisons between experimental data obtained from single-phase gaseous hydrogen cool-down with those computed from a computer program have shown excellent agreements.

A three-part Fortran program for IBM 704 computation of the relative cross sections of isomers produced in nuclear reactions is described. The three subprograms compute the partial compound nucleus cross sections and the normalized initial compound nucleus spin distribution, the normalized spin distribution following particle emission, and the normalized spin distribution following gamma emission. The Fortran listing of the program and cards for a sample problem is included. (D.C.W.)

The magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident are discussed. Each system may include a combination of coaxial loops, cylindrical or plane annular current sheets, and cylindrical coils of rectagular section. Working equations are listed, following an outline of theory. A discussion of errors and of means for reducing them leads to specific suggestions ior use of the method with any programmed computer. An existing comprehensive program for the IBM 7090 is described in detail. The rate of convergence of the harmonic series depends on the ratio R of the polar radius of the field point to that of the current discontinuity nearest the origin. In some cases the precision reaches 1000 parts per million even at R = 0.95, improving to 1 or 2 parts at R = 0.80. Since the origin is arbitrary, the practical range of the method often includes the whole space that is accessible to experiment. For very close approach to the windings one must resort to elliptic integrai methods or their equivalent. Alternative programs …

This brief report (December, 1962) discusses the effect of effluents from the Hanford Production reactors on the water temperature of the Columbia River.

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Several 300 series stainless steels were corrosion tested in raffinate storage tanks made of the same materials. After exposure to the rafflnate solutions for periods of up to seven years, maximum penetration rates of 0.1 mil/ yr were noted. (auth)

The experiments are described in sections on approach to critical, control system evaluation, measurements of fuel worth, measurements of reactivity and other coefficients, flux measurements, power measurements, and measurements of fuel plate, control rod, and graphite temperatures. (J.R.D.)

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Based on process development work at ORNL, a facility was designed for demonstration of the pot calcination process with a variety of high-level radioactive wastes. In this facility, operational and control problems associated with an integrated process can be identified and solved, procedures to improve characteristics of the calcine can be studied, and important aspects of calcine temperature distribution and fission product behavior can be observed. Installation of the facility is planned for the Hanford Atomic Products Operation. The facility can be installed in any cell or cells having certain basic features. (auth)

The test objective is to determine the effect of radiation and temperature on the outgassing rate of tritium generated in a lithium-aluminum alloy by neutron irradiation.

The test detailed in this report authorizes the installation of sampling tubes in the vacant-positions in one of the two front-to-rear graphite stringers to be installed in KW Reactor in January 1963. These lines will permit withdrawal of a gas sample from the active zone at a point where the graphite temperature is being measured. Analysis of this gas sample on the gas chromatograph and on a new catalytic oxygen-hydrogen instrument is expected to yield valuable information on graphite burnout versus temperature and gas quality.

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The failure of a fuel element cladding in one of the water-cooled plutonium production reactors permits the erosion of irradiated uranium metal by the cooling water which is normally disposed to the Columbia River. Monitoring systems at both the reactors and at their effluent basin outlets to the river continuously monitor these streams, and if major fission-products release occurs the coolant can be held in retention basins. In addition to these monitoring systems, a river monitor is located at the 300 area which continuously monitors the gross gamma activity of the Columbia River; however, its sensitivity to rupture debris is limited because of the relatively high background'' from the short-lived (n, {gamma}) produced radionuclides in the river. In making hazard assessments and in providing adequate monitoring techniques and equipment at down-river locations, it is essential to know what changes occur in fission and (n, {gamma}) produced radionuclides following release of rupture products to the river.