Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.

Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).

From introduction: This report on the geology of the Powder River Basin is one of a series of reports by the Geological Survey on sedimentary basins in the United States.

Introduction: The U.S. Geological Survey is appraising the possibility, however slight, that the ground water beneath the Nevada Test Site, possibly contaminated by nuclear detonations, may carry radioactive fission products to places where they may constitute a public hazard.

This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.

This report investigates the "formation of hydrazine from the cobalt-60 gamma radiolysis of ammonia in the presence of mineral solids"--from abstract.

The o-aminophenol, 3-hydroxyanthranilic acid (3-OHAA) is a metabolite of tryptophan normally present in urine in trace quantities. C14-3-OHAA was given to normal mice and mice with either mammary adenocarcinoma, glioblastoma multiforme or ascites tumor to study the influence of these transplantable tumors on metabolism of 3-OHAA.

From introduction: This report is one of three volumes of the first annual progress report on the GE-NMPO high-temperature materials program conducted during calendar year 1961.

From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.

From summary: This report describes the 10-watt Sr-90 thermoelectric generator, the dc-to-dc converter, batteries and the method of installation in the light buoy.

Summary report of final hazards for the Boiling Nuclear Superheater (BONUS) Power Station with illustrations.

"Muon capture rates have been measured in a large number of the heavier elements in recent years. The amount of data available on the light elements, however, is scant. It would seem that lifetime measurements of muons in light elements would be of particular interest with regard to understanding the nuclear structure and determining the strength of the weak interaction. Furthermore, only one previous measurement of the muon capture "'isotope effect" has been done, that being for chlorine isotopes. In view of these considerations, the series of muon capture experiments reported in this paper was undertaken."

A radioisotope method has been used to measure the flow in the light water circuit of HIFAR. A mean value of 756 pounds/sec was obtained which is in fair agreement with conventional Dall tube method. Attempts to measure the flow through individual cooling towers were not entirely successful, but some useful information was obtained.

The reactor transfer function of HIFAR has been measured at low power and compared with the calculated response determine the prompt neutron lifetime. Lifetime values in the range 600 to 800 microseconds, depending on the position of absorbers withing the core and reflector , were obtained with an estimated error of less than 100 microseconds.

Technical report giving an overview of the use of nuclear energy to produce chemicals including a rough estimate of the economic potential.

Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.

Abstract: Urine uranium excretion data for persons exposed to uranium by inhalation are analyzed Data from both chronic and single massive exposures are included, and a generalized excretion pattern, applicable to any uranium compound absorbed by inhalation, is proposed. ...It is shown that it is not usually practical to use urine samples to monitor individual exposures. Such an evaluation is possible only with a suitable series of samples collected at known intervals past the exposure. It is also shown that it is not possible to determine chronic exposure levels from routine urine samples. Chronic exposure levels and body burdens can only be estimated with a sample series collected two or more weeks after the termination of exposure.

Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and training program outline.

Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and a training program outline.

Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."

From introduction: "Following the USSR announcement of its intention to resume testing, arrangements were made for the three stations collecting individual rainfall samples to begin analyses for short-lived nuclides. Some of the data are now available and are reported here." From Data: "The available data, including samples for Houston, Texas and Louisville, Kentucky are given in the tables at the end of this report."

Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution, vibrational compaction procedure, sheath thickness, and fuel element shape on the maximum obtainable density were investigated."

From abstract: "The optimum conditions for preparing sodium ethylsulfate from sulfuric acid, absolute ethyl alcohol and sodium hydroxide have been determined."

From abstract: "A single focusing mass spectrometer has been converted into a double focusing instrument. Relatively high resolution is obtained by decreasing the slit widths and minimizing the ion-optic aberrations. A relatively low ion accelerating voltage (2000 volts) is utilized compared to those normally used for high resolution work. The entire construction was performed at these laboratories. Essentially all of the original equipment was reused in the double focusing system. Although the original source slit was decreased from 10 to 0.4 mils and the source α value was decreased from 0.04 to 0.008 radians, sufficient sensitivity is obtained for quantitative gas analysis with the ordinary electrometer tube amplifiers utilizing 4 x 10[^]10 ohms input grid resistors and 100 per cent inverse feedback. Carbon monoxide-nitrogen mixtures were analyzed quantitatively. The results indicate that direct quantitative analysis can be obtained on mixtures ranging from 99 per cent to 10 per cent carbon monoxide in nitrogen. Analysis of lower percentages may be made possible through indirect reading of the peak should it be necessary. It appears that the instrument should be adaptable to research problems concerning these two gases. The immediate problem posed is the analysis of oxygen and nitrogen in metals. Other …