The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.

aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of course depend on specific factors such as core materials and design of the reactor/. Aluminum appears particularly attractive for cladding the cores of aluminum-plutonium alloy proposed for the Plutonium Recycle Test Reactor since, in this case, the physical characteristics of the core and cladding would be practically identical.

This report presents an equation used for calculating the radii of non-spherical cavities formed by underground nuclear explosions.

A repeatable technique for preparation of thin, self-supporting copper films has been developed at the Lawrence Radiation Laboratory in Livermore, California. The process, done in a vacuum chamber, involves evaporation of copper by electron bombardment, and deposition of the copper on a detergent-coast glass substrate. The copper film is later removed from the substrate by immersion in water.

This is a report of work completed during the period October 1, 1961, to December 31, 1961. The Program fuel element was completed and assembled. After extensive analysis, it was concluded that the fuel was satisfactory for use in the Program.

An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.

In a continuation of the study of the properties of the φ meson we have roughly doubled the available data on the φ production via the reactions [equations were not transcribed]. The data discussed here was obtained in the Brookhaven National 20" Hydrogen Bubble Chamber exposed at a separated beam of K- of 2.24 Gev/c.

The efficiency of multiple traversal targets is defined as the probability that a proton dies by making a nuclear collision in the target rather than by hitting the limit of the synchrotron aperture. The efficiencies of Be, Al, Cu, and Pb targets are shown for 15 and 30-Bev protons in the Brooknaven AGS. Beryllium was found to be the most efficient. (M.C.G.)

This report discusses the alternating gradient synchrotron at Brookhaven National Laboratory and provides a preliminary discussion on experiences to date and experiments in progress.

This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Alloys are being produced by sintering pressed powder aggregates with subsequent arc melting. Alloys have been made at two atomic percent intervals up to thirty atomic per cent carbon. In the future, higher carbon compositions are to be investigated. Techniques have been worked out for the metallographic preparation of the extremely hard and friable alloys.

Introduction: "This report presents physical property analyses for 28 additional samples and is a supplement to Geological Survey Technical Letter: Area-12-1, which gave a brief summary of the geology, descriptive data on the tunnel, and X-ray, chemical, semiquantitative spectrographic analyses, and some physical properties determinations of samples collected in the U12g.01 tunnel."

From introduction: "Preliminary design and analysis of the 300 MWe core."

Based on the assumption that the noise contribution of a semiconductor detector is due solely to the bulk properties of the semiconductor, equations are presented which indicate the theoretical limits of noise in detector-amplifier combinations. These equations show that an optimum amplifier time constant and detector bias voltage exist for which condition the minimum noise is independent of the semiconductor resistivity. The optimum performance of a detector-amplifier system is shown to depend only upon detector area, input capacity (less detector capacity), semiconductor minority carrier lifetime, and the transconductance of the amplifier input tube. A new detector structure including a guard-ring electrode as an integral part of the detector structure is described which largely eliminates noise due to surface leakage. Experimental results for detector leakage and energy resolution are presented which agree well with theory.

From Abstract: "The data for gummed film fallout measurements through December 1959 are reported. The bulk of the report consists of summary tables for each gummed film station listing the monthly estimates of strontium 90 deposition and infinity gamma dose."

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities

The object of this report is to acquaint the operator with the operational and technical aspects of the beam current integrator as well as the theory of the system operation. The design and operation of a beam current integrator are described, and the theory of operation is discussed. The instrument has two channels. The console channel is designed to measure the accumulation of charge received by a target during a period of a day no matter what the range used in the experimenter's channel. An analysis indicated that this unit will measure the accumulation of charge by a target to an accuracy of 0.1215% assuming that the constant error due to shorting the integrating capacitor is accounted for. The instrument is ranged to handle from 0.5 to 500 mu a of beam current. (M.C.G.)

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.

The phase shifts for proton-proton scattering as calculated from the one-pion exchange contribution (OPEC) alone are of some interest because they describe the scattering correctly in the high angular momentum states, and because in the lower angular momentum states the deviation from the OPEC phases is an indication of the strength of the two-pion and higher exchanges processes. The attached table gives the proton-proton nuclear-bar phase shifts as calculated from OPEC. Phase shifts and mixing parameters are given in degrees, as function of the T, the laboratory kinetic energy of the incoming protons in Mev. Phase shift and mixing parameters are listed in the angular momentum states.

Abstract. Results are presented of a theoretical study to calculate the [alpha]/[beta] ratio of filter-collected natural airborne radioactivity. The detection of airborne plutonium contamination by noting increases in this [alpha]/[beta] ratio is discussed. A modification of this approach which provides a more uniform response to alpha airborne contamination is described.

Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e. g. wire-wrapping around a cluster of cylindrical fuel rods. This form of corrosion is defined as corrosion occurring at contact areas and as such, fretting of Zircaloy-2 could take place in many reactor concepts. This report details the results of testing performed to induce fretting corrosion of Zircaloy-2 and the direction of the future tests.

The following quarterly report covers the period during February 16 to May 15, 1963. This report is divided into sections covering the separate activities during this period, studying the thermal behavior of the F-center in RbCl.

From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.