The power supplies designed and constructed to power high-intensity flash tubes are described. Three supplies, capable of charging 100 mfd to 2 kv with a repetltion rate of not less than 0.8 sec, are operated remotely from a control panel containing 3 powerstats. The power supplies are full wave center trapped rectifiers employing silicon rectifiers. (M.C.G.)

A test report on the brittleness of borated steel to be used in the KIWI B-5 shield capsules.

The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)

A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)

Because of the questionable performance of the 190-DR steam backup system during the power outage of April 6, 1962, it is felt that a general review of the DR secondary water system capabilities and the standby status of the pumping units is warranted. This report shall briefly describe the performance of the steam backup system during the April 6 power outage and the subsequent power outage of July 10, 1962. Since the former outage, tests have been conducted on the steam pump units to determine their capabilities; the test results are presented in this report. A statement of the generally accepted criteria for secondary coolant system adequacy is included and recommendations for meeting the criteria at DR reactor are presented.

In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta heat treat facility and autoradiograph film developer. Manpower savings will result principally from refinement of each operation. There are no really outstanding areas for improvement. The greatest potential for savings is in material costs. These are illustrated in Tables I&IV. Maintenance costs provide for possible significant reductions at braze, vacu-blast, nondestructive test, autoclaves, and chemical processing equipment.

One of the major unsolved problems affecting the life of the SNAP II Power Conversion System is the mass transfer of corrosion products by mercury and subsequent deposition. It is feared that the corrosion products might tend to accumulate in critical areas such as orifices, bearings and so forth. Therefore, this test was conducted to evaluate a corrosion product separator and to determine the influence of corrosion product removal on corrosion rate. The corrosion product separator was successful in removing 85 percent of the elements corroded from the container walls. The loop and separator, both fabricated from Haynes alloy No. 25, operated for 1000 hours. The mercury was boiled and condensed at 1100 deg F, superheated to 1190 deg F and subcooled to 325 deg F. The flow rate in this loop was much higher than in previous loops, being approximately 37 pounds of mercury per hour as contrasted with approximately l2 pounds of raercury per hour. No increase in corrosion rate was noticed as a result of the higher flow rates and velocity or by the removal of corrosion products. If this type of separator or an improved type works equally as well in the final application, the danger …

A study of the incorporation of {sup 14}CO{sub 2} into cell components of synchronously growing Chlorella pyrenoidosa has shown that DNA is synthesized primarily during the latter stages of the cell cycle prior to cell division. RNA was synthesized at an approximately equal rate during each of the three phases of the cell growth studied. No major differences were noted in the incorporation of {sup 14}CO{sub 2} into the soluble cell components in these long-term incorporation studies.

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Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)

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Isotopic assays have been made on the Cr in samples from 14 different chrominiferous minerals from different geographic and meteoritic sources. The results of the assays indicate that it is not possible to state unequivocally that variations in isotopic composition have been observed. (auth)

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)

Possible experiments that could be performed at the Brookhaven alternating gradient synchrotron using highenergy deuterons and heavier nuclei are reviewed. Particular attention is given to production of high-energy neutrons by stripping. A brief analysis of changes needed to accelerate heavier nuclei reveals such modifications would not be prohibitive. (D.C.W.)

Maintenance of poiarization of polarized protons in a linear accelerator is known to be feasible. Circular accelerators present a different problem, and the investigation of the interaction of orbit dynamics and particle polarization in general is undertaken. The equation of motion of the spin vector of a charged particle in a magnetic field as formulated by Bargman, Michel, and Telegdi is utilized in the study of depolarization for several accelerators. High values of depoiarization are obtained, and means for avoiding such depolarization are suggested. (D.C.W.)

This report covers only the tests and operations to be conducted with SNAP 10A system; acceptance tests of SNAP 2 and 8 systems, which will also be conducted in this facility, will be presented in an addendum to be published at a later date.

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.

On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing the men were released to return to work. In compliance with AEC Manual Chapter 0703, an AEC-HAPO committee composed of two AEC employees and five General Electric employees was appointed by the Manger, HOO, with the concurrence of the General Manager, HAPO, to conduct an investigation of the incident. The committee`s purpose was to determine the cause, nature, and extent of the incident, and recommend action to be taken by others to minimize or preclude future incidents of this magnitude. A study of operating practices and operating conditions that appeared to exist prior to, during, and subsequent to the accident was made by the committee. The committee believes that this report provides sufficient information to answer questions which may arise as a result of the criticality incident …

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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.

Work was carried out to obtain significant data on reactor excursions, in particular the SL-1 excursion, to extend the analysis of reactor transient behavior so as to obtain an improved understanding of the thermal and mechanical processes that take place during and following a reactor excursion, and to obtain chemical, metallurgical, and nuclear data relative to the pre-accident performance of the SL-1. Laboratory investigations were made of samples of the SL-1 power plant. Results are given and their significance discussed. An attempt was made to construct a mathematical model of reactor excursions, based partly on fundamental thermodynamic and nuclear considerations, and using some empirical results. This model was applied to SPERT and BORAX excursions with some success. Recommendations concerning reactor design and operation, which have arisen from the SL-1 accident and its analysis, are summarized. Results are presented in tables and graphs. (M.C.G.)

The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New parameters are derived in this document for future total control calculations.

Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)

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)