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630A Maritime Nuclear Steam Generator Scoping Study

Description: 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.
Date: April 6, 1962
Creator: General Electric Company. Flight Propulsion Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Absorber Burn-Up Experiment. Final Report

Description: 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)
Date: April 1962
Creator: Russell, J. L. Jr.; Carrothers, M. R. & Mosgovoy, W. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accidental nuclear excursion recuplex operation 234-5 facility: Final medical report

Description: 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 contin… more
Date: April 7, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

Description: 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.
Date: April 1, 1962
Creator: Rider, B. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: 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 li… more
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: 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 be… more
Date: April 1, 1962
Creator: Arthur, J. R., Jr. & Hanson, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Description: 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).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Air flow inspection of Rover fuel elements

Description: 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.
Date: April 11, 1962
Creator: Blanks, J. R. & Wright, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anion exchange flow sheets and equipment for recovery of Task I filtrates

Description: 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 Butt… more
Date: April 23, 1962
Creator: Crocker, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Application of Wax Laps to Vibratory Polishers

Description: 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."
Date: April 19, 1962
Creator: Hopkins, E. N. & Peterson, D. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1961, January andFebruary 1962

Description: 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 … more
Date: April 3, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Biological and Medical Research Division Semiannual Report July Through December 1961

Description: 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 epox… more
Date: April 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Boiling Potassium Heat Transfer Project Loop Design and Development

Description: 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.
Date: April 30, 1962
Creator: Chen, John C., 1934-2013
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Boron Carbide-Graphite Nuclear Control-Rod Material: Preparation, Thermal Stability, and Irradiation Evaluation

Description: 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 de… more
Date: April 24, 1962
Creator: Goeddel, W. V.; Lonsdale, H. K. & Meyer, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Brookhaven Chemonuclear in-Pile Test Loop

Description: 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.
Date: April 23, 1962
Creator: Tucker, Walter D.; Waide, C.; Bezler, P. & Steinberg, Meyer, 1924-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Budget Estimate for Fiscal Year 1964

Description: 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.
Date: April 18, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

C reactor overbore fuel failures

Description: 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.
Date: April 30, 1962
Creator: Ambrose, T. W. & Graves, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculation of Departure From Nucleate Boiling Conditions for the Spert Iii Reactor in the High Pressure Region

Description: 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-Nelso… more
Date: April 18, 1962
Creator: Dugone, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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