From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.

Experimental results are presented of pile oscillator measurements of cross sections of irradiated samples of seventeen elements. Mass spectrometer analysis of some samples was performed. Quantitative theory-experiment correlation yielded thermal absorption cross section information and also established the reliability of control rod lifetime calculations for each element investigated. Application of the results to calculation of the nuclear lifetime of reactor control rods is discussed. (auth)

Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.

The April 7, 1962 criticality accident involving human exposures was the first to have occurred in any production facility at Hanford. The accidental nuclear excursion did not result in any mechanical damage or spread of contamination. Three employees received over-exposure to gamma and neutron radiation. None were fatally exposed and in each case the over-exposure was recognized promptly. Following an initial period of medical observation and testing, the men were released to work. They continued to be followed clinically. Clinical studies performed were hematological procedures including leukocyte chromosome aberrations, morphologically aberrant blood cells, bone marrow evaluations, blood chemistry determinations, amino acid excretion studies, seminal fluid, urinary gonadotropins and estrogen excretion studies, testicular biopsies and crystalline lens examinations. These studies, along with a brief description of the accident and of the dosimetry, are summarized in this report by those participating in the studies. In view of the dose ranges received in these cases, both the negative and positive findings are considered to be of unusual interest due to the lack of knowledge of effects following human exposures at these levels.

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.

The report includes a summary of the results of computations to data on post-test dose rules from activated materials comprising system components and support structure.

The adsorption of ethane, ethylene, and acetylene on clean iridium in a field emission microscope was found to cause characteristic changes in the work function of the iridium surface. Further changes, which were time and temperature dependent, resulted when such surfaces were heated. Flash filament experiments showed that the changes in work function upon henting are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it was possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results were consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desorption of the adsorbed hydrogen. At very high temperatures the remainlng carbon atoms are removed, presumably by evaporation. (auth)

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."

First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).

This report addresses the concepts of the Aeroject-General Corporation Reliaibilty Handbook

This report addresses two inspection systems that have been constructed which use strain gage pressure transducers to pick up changes in static pressure due to change in the hole diameter.

From Abstract: "The electric field is plotted and its construction steps for axial symmetry are given."

The filtrate stream from the precipitation--filtration step of the Button Line process must be recycled to recovery operations to reclaim residual plutonium. Present practice is to transfer the filtrates to Recuplex, concentrate by a factor of 6 to 10, and blend into the feed stream for solvent extraction purification. Limited tankage is available for solution storage. Interruption of Recuplex operations necessitates termination of operations in the precipitation-filtration steps and other Button Line areas. Filtrates can be recycled to one of the parent solvent extraction plants for recovery. However, excessive handling operations are encountered by this processing method. This document describes the anion exchange flow sheets and equipment for processing the filtrate stream without dependence upon other recovery operations.

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1961, activities, finances, organizational leadership, and other information about scouting programs.

From introduction: "In this paper the adaptation of the wax lab surface vibratory polisher is described. The wax lap requires little maintenance during the life of the lap. It is not necessary to remove any of the holding devices on the bowl to clean and recondition the lap. The bowl is merely washed out, recharged and placed in operation. The wax lap will not wrinkle or tear, nor is it necessary to change it each day such as the silk or nylon cloths."

It has been known for a hundred years that formaldehyde polymerizes to carbohydrate substances in alkaline media. Although the reaction has long attracted much attention, only recently has a detailed qualitative analysis of the products been carried out by chromatographic methods. We have started to re-examine this reaction by combining chromatography with radioactive tracer techniques in the hope of refining the quantitative aspects of the analysis. Our particular interest has been to develop methods for determining the relative proportions of ribose and ribulose in the mixtures of sugars formed in basic media, as well as under other polymerizing conditions. The finding of large amounts of these sugars might help to explain the occurrence of ribose as the only basic sugar in the fundamental replicating molecules--the nucleic acids. Formaldehyde is thought to have been present in the primitive reducing atmosphere which existed before life first appeared. The ribonucleic acids must have appeared in the constitution of reproducing systems at a very early stage in the development of living organisms. In this study, the polymerizations of formaldehyde were carried out in calcium hydroxide suspensions at 40{sup o}. Aliquots of the reaction mixtures were withdrawn at after various time intervals and the alkali …

Thirty-seven articles are included; separate abstracts were prepared for 24. Two articles on the effects of radiation on methionine sulfonium compounds and on silica gel structure and the chromatographic process were previously abstracted in NSA. The articles not abstracted include information on life span and fertility of irradiated mice, biochemical studies on Cu(I,II)-peroxy theory of radiobiological effects and their modification, studies on the giant amoeba, low temperature storage of epoxy resins used for embedding in electron microscopy, method for obtaining fixing solutions osmotically equivalent to physiological saline solution, and P/sup 32/ uptake as an indicator of tritiated thymidine toxicity. (P.C.H.)

This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.

Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-pressing techniques. The densities of these compacts decreased with increasing B content. Compact strengths, however, were noticeably increased with B content of 20 wt%, suggesting that the B acts as a sintering aid. Thermal stability was evaluated by annealing compacts under a variety of temperature and atmospheric conditions. The upper limit of the ioss of 13 was 5% to 10%~ in 200 hr at 2000 deg C--considerably less than would be predicted from the Langmuir evaporation equation. Diffusion of B atoms through the pores of the graphite, rather than evaporation from the surface, was found to be the rate- controlling step in the loss of B. Compacts containing 20, 30, and 40 wt% B were irradiated at 350 and 700 deg C to 1.0 and 2 4 x 10/sup 21/ nvt(fast). Physical integrity of the compacts was good after irradiation. Slight increases in tensile strength were noted in several instances. (auth)

Technical report outlining the plan to develop the Brookhaven chemonuclear in-pile test loop because the interest in utilizing reactor radiation energy (fission-fragment recoil and neutron-gamma) for production of chemicals has developed to the point where a loop to study chemonuclear system in a reactor under dynamic conditions is necessary.

The stated objective of the SNAP-50 reactor and primary system development program is the design, fabrication, development and test operation of a series of reactors and associated equipment leading to a fully qualified and accepted SNAP-50 flight reactor and primary system.

The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.

Calculations are made to determine the safe steadystate power operating limits of the Spert III reactor from the viewpoint of fuel plate burnout. A computer program is developed for the IBM 704 to aid in these calculations. The Bettis design departure from nucleate boiling (DNB) equation is used in conjunction with the LeTourneau and Grimble method of hot channel'' analysis in the development of the calculations. For cases where DNB occurs in the bulk boiling region, a modified Martinelli-Nelson twophase flow correlation and some experimental singlephase pressure drop data are employed. DNB for a typical operating condition of 550 deg F inlet temperature and 2500 psig is computed to check the code. The results of the sample calculation show that at a steady- state power level of 60 Mw (maximum design power) the minimum flow rate required to prevent DNB is approximately 8000 gpm. (auth)

It is noted that in high-temperature He-cooled graphite reactors, sufficiently high levels of gaseous impurities can lead to transport and corrosion effects. The possible effects of these reactions in graphite-moderated reactors designed to operate at a He-coolant pressure of a about 20 atm. were investigated. Results are included on C transport, steam-graphite reactions, and deposition of C on surfaces. (J.R.D.)