Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.

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 …

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

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.

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

"This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.

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.

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."

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

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: 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."

"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."

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.

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

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.

From introduction: "Describes progress in the development of radial vane primary separators following initial work reported in GEAP 3564."

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

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.