A micrometer that utilizes eddy current techniques is described. The gage is capable of measuring nominal 0.5000-in. aluminum rods to an accuracy of plus or minus 0.00005 in., and is unaffected by residual nonconductive surface filins such as oxides or corrosion products. (auth)

The 9 single-crystal elastic moduli pertaining to principal crystallographic axes of alpha U at 25 deg C were determined from measurements of high-frequency wave velocities for 21 modes in seven single-crystal specimens, using the phase-comparison method of McSkimin. From the results the elastic compliances, compressibilities, and Poisson"s ratios were computed for the principal axes. Th variations with crystal direction of the stiffness moduli, Young's moduli, and rigidity moduli were plotted. The nature of the anisotropy for the different moduli indicated that the nearest neighbor interatomic bonds are considerably stiffer than the next nearest bonds, which are only slightly larger in interatomic distance. (auth)

Abstract: This memorandum presents the possible applications and instructions for using REDCROSS, an IBM-704 computer program.

A process for separating americium and curium from rare earths by anion exchange based on selective chloride complexing was developed and tested on a laboratory scale. The separation is accomplished by sorption of americium, curium, and rare earths on Dowex 1-10X resin from a solution of 8 M LiNO/dub 3/ followed by selective elution of rare earths with 10 M LiCl and americium-curium elution with 1 M LiCl. In a laboratory demonstration of this process, greater than 99.5% of americium tracer containing no detectable amounts of rare earths was recovered. (auth)

A simple laboratory apparatus for the study of fissiongas release from neutron-activated fueled graphite was developed. Xenon-133 released from a heated specimen is carried in a helium sweep gas to a charcoal trap, where the accumulated activity is monitored continuously by a scintillation detector, ratemeter, and pen recorder. The maximum specimen temperature (2500 deg F) is achieved in 10 min with an induction heater. All instrumentation is commercially available. Data for several neutron-activated fueled-graphite specimens heated in the range from 800 to 2500 deg F are presented to illustrate the typical results obtained with the apparatus. (auth)

As part of an earlier program of investigation in this laboratory, studies were made of the gamma ray spectrum and the beta ray spectrum of cerium-144. In the present work, seme coincidence studies were made on one of the beta groups appearing in the cerium-144 decay and on the gamma rays appearing in the deexcitations from the energy levels of praseodymium-144. Sources of cerium-144 were prepared frcm carrier free radioactive cerium-144 as supplied by the Oak Ridge National Laboratory. The sample material was more than two years old at the time of preparation of sources. No additional chemical purification was attempted. Sources for use in the beta crystal spectrometer were mounted on thin Formvar film on spectrometer ring mounts. The gamma ray spectrum of cerium-144 in the energy range 20 kev to 180 kev is shown in Figure 1. This spectrum was determined using a 2-inch by 2-inch NaI(Tl) crystal. The pulse spectrum was analyzed by a Radiation Instrument Development Laboratory (RIDL) 200 channel analyzer. The spectrum gives clear evidence of gamma ray peaks at 34 {+-} 3 kev and 134 {+-} 2 kev. A rather broad peak at 80 kev is observed. An indication of a gamma ray group …

The development of high-energy charged particle accelerators such as the Bevatron and of improved nuclear-event detection devices such as the Berkeley 72-in. hydrogen bubble chamber has greatly increased the need for high-speed data reduction of nuclear events. Full exploitation of the potential of the 72-in. bubble chamber demands a very high-speed analysis system. This paper describes an approach to such a system.

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From abstract: Many residents of the Nevada area carried film badge radiation dosimeters during Operation Plumbbob in 1957. Badge readings in specific localities appear to follow the logarithmic-normal distribution.

A design concept is presented for an electrical system using two SNAP III type generators fueled with cerium. In the modified SNAP III generator, a capsule of Haynes 25 contains 9725 curies of cerium oxide pellets, which will provide 67 thermal watts at time of launch. Sufficient void volume and capsule strength ensure containment of the oxygen evolved through isotops decay during the operational life of the generator. Thermal converter configuration in the conceptual generator is identical to that of the SNAP III except that the shell is stainless steel. Two methods of biological shielding are considered. The first uses mercury contained in a sphere surrounding the generator. In the second concept, a lead cask shields the unit until its installation in the launch vehicle. A remote installation procedure and an equipment arrangement are proposed. Generator output predictions were based on actual test data. The output of a single unit would be 3.8 watts at launch, decreasing to 1.9 watts in the course of a 6-month mission. A groundhandling procedure and conceptual designs of the equipment are included. (auth)

A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high temperature.

The control rod drive mechanisms and associated instrumentation in the Shippingport PWR were in satisfactory operating condition. Deficiencies that were observed during the test and subsequently corrected were: no positive indication of movement in rods 11, 82, 62, 53, and 14, as shown on the rod position indicating lights; and the bottom indicator coil for rod 81 was connected improperly. After the deficiencies were corrected, the test was rerun for the rods in question and all operated satisfactorily. (auth)

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Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Two thermoelectric generators that use Cm/sup 242/ as the heat source are described. One, designed for a lunar 12,480 c. The second, designed for a satellite or space probe mission, is fueled with 6.18 g having an activity of 20,400 c. Preparation of the fuel, assembly of the generator, and the launching of the vehicle are considered. Accidents that may occur in the launching of the vehicle are analyzed and the fate of the fuel in the event of an aborted mission or upon reentry of the vehicle after the completion of a mission are determined. (W.D.M.)

Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)

An investigation was made of the feasibility of measuring thorium in rock samples by use of scintillation spectrometry facilities available in the ORNL Analytical Chemistry Division. Results of measurement of eleven samples indicate that the method is usable and that agreement with chemical analysis is reasonable. (auth)

A test was made to determine radiation levels in the reactor pit and canal walkways with the reactor pit filled to various levels. Temperatures at several locations on the floor of the reactor pit while the reactor was at power were also measured. Draining all shielding water from the pit while the reactor was at approximately 39% of full power did not result in a radiation hazard on the canal walkways. When the reactor pit was completely drained the highest radiation levels were found above the outside edge of the reactor dome approximately 25 ft from the pit floor. The temperature of selected bolts and the surrounding concrete at the base of the reactor dome did not increase when all the water was removed from the reactor pit. (W.L.H.)

Report concerning the results of an experiment that determined the masses and velocities of over 20,000 objects and laboratory animals by simulating the blast winds of nuclear explosions.

Report issued by the APDA over studies conducted on the Doppler Effect in fast neutron reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.

Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem

Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.

Two fused chloride salt eutectics, binary LiCl-KCl and ternary NaCl- KCl- MgCl/sub 2/, were used in fuel processing studies as part of the Liquid Metal Fuel Reactor research and development program. Results of engineering work done at Brookhaven since 1950 are summarized. It was demonstrated that fused chloride salt technology is sufficiently developed so that loops and other experimental equipment can be designed and operated at 500 deg C with a high degree of confidence. The equipment, which was operated for many hours, included a large forced-circulation loop and many thermal-convection loops and tanks. The specifications used for the fabrication, cleaning, and testing of equipment for salt service are described. All welded systems, welded by the usual inert-arc procedures, are preferred, but ring type joint stainless-steel flanged connections were found satisfactory, mainly for connecting melt tanks to experimental equipment and for mounting orifice flowmeters. The surfaces of equipment to be used with fused salts were cleaned satisfactorily prior to assembly by several different methods, but sandblasting was found applicable to all types of equipment. Radiography was used to check all welds in contact with fused salt for flaws and, during operation, to locate and determine the cause of any malfunction. …