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Use of that portion of the characteristic curve of photographic film in which transmission is linear with log exposure eliminates the distributional error and thus makes possible the assessment of total mass of an inhomogeneously distributed cell consistent without scanning or measuring the cell's projected area. Measurement consists of obtaining the difference in output of a photocell receiving the total light transmitted by a photomicrograph of the cell, and a photomicrograph of the microscope field illumination against which the cell was photographed. A method of making such measurements is given, and its basis is described.

Details concerning a recommended system of flow-plan symbols and drawings are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. (J.R.D.)

This report supersedes ORNL CF-57-2-1, which was an extension and revision of ORNL CF-54-6-72. Details concerning a recommended system of flow-plan symbols and drawing are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. The system is a modification of the Instrument Society of American Recommended Practice (RP 5.1).

Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.

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The heat exchanger of the calciner consists of a vessel into which unfired, horizontal, bayonet tubes extend in a fluidized bed. Strain measurements were taken on several of the tubes under simulated operating conditions and the associated dynamic stresses were calculated. Vibrations greater than design limitations for indefinite operation were found to exist. To restrict these vibrations and prevent further tube fatigue cracking, a tube support was installed. Since the installation of the support, the calciner has operated satisfactorily over 1275 hours. (auth)

This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.

This technical report discusses processes to study the stability constants and intrinsic solubility of several Nickel(II)-vic-Dioxime complexes.

The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests performed for objective No. 1.

Early effects obtained with monoenergetic fast neutrons in mice have been described elsewhere. Emphasis in this report will be placed on the late effects of lens opacification (cataractogenesis), particularly during the period soon after irradiation with low or fractionated doses of neutrons at two energy levels, or X-rays. Considerations will also be given to the influence of age at time of irradiation upon the induction of lens opacities. Both studies are continuing, with periodic slit-lamp microscope examinations, but findings to date warrant this initial report at this conference.

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Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding. This diffusion is likely because of the 600 deg C heat treatments used in the conventional fabrication process. Uranium determinations based on neutron activation analysis of machined layers from fuel plate surfaces showed that rolling-mill equipment, contaminated with highly enriched uranium, was responsible for transferring as much as 180 ppm U to plate surfaces. By careful practice where cleanliness is emphasized, surface contamination can be reduced to 0.6 ppm U/sup 235/. The residue remaining on the plate surface may be accounted for by diffusion of uranium from the fuel alloy into and through the cladding of the fuel plate. Data obtained from preliminary diffusion studies permitted a good estimate to be made of the diffusion coefficient of uranium into aluminum at 600 deg C: 2.5 x 10/sup -8/ cm//sec. To …

Selected components from a staianless steel nonregenerative heat exchanger removed from the U.S.S. Nautilus (SSN571) have been examined for evidence of stress-corrosion cracking. The examination was conducted on three baffle plates, all primary-face seal welds, and the tubes and the surrounding tube sheets of 7 out of a total of 35 tubes. Maximum operating temperature of the heat exchanger was 260 ction prod- F for the inlet primary water and 164 ction prod- F for the exit secondary water. Chloride content of the secondary water averaged 5 ppm, with a maximum of 15 ppm. Only one suspected stress-corrosion crack was found in the components normally in contact with the secondary water. The crack, 2.5 mils in depth, was located on a fully exposed tube. At the 95 per cent confidence level this represented a probability of finding cracking on fully exposed surfaces in 0 to 60 per cent of the rest of the tubes in the heat exchanger. Severe stress-corrosion cracking was found in tubes in the tube-sheet drain area at the juncture with the inner tube sheet at the inlet end, where secondary water seeped past the expanded tubes. Cracks were detected in five of seven tubes for a …

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A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)

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Data are presented that show a marked species difference in the degree of damage and in the course of events seen in the bone marrow and peripheral blood after a given dose of radiation. The data taken together indicate strongly, but do not prove, that the picture seen results primarily from damage to the stem cell population. This damage to the stem cells is manifested later in the more mature differentiating cells of the marrow, and in the peripheral blood. The picture seen results both from death of stem cells, and also injury leading to reduced proliferative capacity, with later death of the injured stem cell and all of its progeny. Thus the picture seen is a result of both quantitative and qualitative changes resulting directly from the exposure of the stem cells, and species differences relative to sensitivity and time course of events appear to depend to a large degree on differential sensitivity of the bone marrow stem cell populations to death and injury. (auth)

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The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditions common also to the side and bottom thermal shields. Concern for possible deteriorating condition of the top cooling tubes has increased with the discovery of a leaking cooling tube at the C Reactor. This report provides information of the present condition of the cooling tubes and discusses continued surveillance of their condition which is required for evaluation of their continued serviceability.

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This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.

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