This technical report is intended as a brief description of the free convection problem existing in the various annuli of the SIR Mark A rotating plugs. It is by no means a complete report of the plug "hot tests", but merely records some of the more significant experimental observations and presents a few of the theories and calculations made to explain the observed free convection phenomenon. The general discussion which follows is chronological. Details of analyses are relegated to the Appendix.

The problem of a blast wave propagating through an inhomogeneous atmosphere is set up for computation by the CRC LORA. Previous treatments of this problem have used various simplifying assumptions such as that of purely radial flow. Since, however, pressure gradients in this situation will not in general be in the direction of rays from the blast center, non-radial flow will exist, and there is reason to believe that for large distances this effect will play a prominent role. Therefore, a program was set up for the numerical calculation (on the CRCLORA) of the propagation of a blast wave from a ground burse with altitude effects and possible tangential flow taken into account. With initial conditions known, the program is designed to give the pressure, density, radial and tangential flow velocities after successive time intervals at 16 equally spaced positions on each of 16 straight rays emanating from the point of burst. These positions are shifted with time to keep up with the shock front. Rehmeyer's and Van Neumann's method is used to handle the discontinuous shock front. In this method an artificial viscosity term is introduced in the the equations of motion in order to smooth out the discontinuity, …

This method essentially consists of analyzing x-ray filtration data in terms of Laplace transforms and obtaining the spectral energy distribution in terms of a sum of the corresponding inverse Laplace transforms. Some of the functions which are especially suited for this application are given and a graphical method of analyzing filtration data in terms of these functions is described. Examples of the practical application of this method to several low energy x-ray machines are included with a discussion of the advantages, disadvantages, and probable uncertainties which are involved.

The primary purpose of these researches was to clarify the various functions of organic substrates in bacterial photosynthesis. The following aspects were investigated; (1) metabolic pathways under photosynthetic and oxidative conditions, (2) energy transfers occurring during the metabolism in cell free extracts, and (3) the relationship between photosynthetic rate and light intensity for selected organic substrates. The results of these investigations were summarized in a paper entitled "The Application of Carbon-14 to Studies on Bacterial Photosynthesis" which was submitted to the United Nations as a contribution to the International Conference on the peaceful Uses of Atomic Energy, Geneva, Switzerland, August 8-10, 1955. A reproduction of this paper constitutes a major portion of this report.

This technical report describes a simple way to calculate numerical values of K and l shell photoelectric absorption coefficients (averaged over subshells) for highly ionized atoms.

This is the thirty-seventh progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of June 1, 1955 through August 31, 1955 is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) Elementary particle scattering group, (6) Neutron physics group, (7) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Synchrotron group, (11) Theoretical group, (12) Personnel listing.

"An apparatus using a silica Bourdon gage is described for the measurement of vapor pressures or dissociation pressures with an accuracy of 0.1 mm and 0.1 deg C up to maximum pressures of atmospheric or beyond and maximum temperatures of 650 to 1250 deg C. The method is applicable to corrosive substances, to substances whose vapor pressure is sensitive to slight changes in composition, and to substances difficult to purify of volatile contaminants which affect the vapor pressure."

"A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented."

In this paper we are concerned with the potentials and electrical currents flowing at an interface between two phases as a result of chemical reactions which promote selective ion migration. Although our immediate concern is an explanation of the available results on smelting, a sufficiently broad understand requires that we go far beyond this limited results and bring together the findings from many related fields. We first must consider the diffusion of particles across an interface, which for convenience we will speak of as a membrane since convection currents usually stir both phases except for a thin boundary layer.

An analysis to screen the various particle-collection systems which might be used for sampling the upper atmosphere with a rocket sampling vehicle has been undertaken. Although the current model of the Goetz Aerosol Spectrometer is not suitable, a high-flow-rate sampler of this general type, if it can be designed, appears promising. The design of such a sampler will be undertaken in future work. If a workable design is possible, this method would appear to be the most promising of all.

The relation between the maximum permissible transverse energies of particles that can be focused, the azimuthal energy, and the beam width is discussed relative to Megatron coil design. It is shown that deep potential wells for focusing can be obtained only at the expense of a narrow beam. (C.J.G.)

The purpose of the survey was to determine the radiation levels in the 1 D Boiler Chamber during plant operation. The conclusion of this survey is that the radiation level in the 1 D Boiler Compartment with the 1A, 1B, and 1C Main Coolant loops in service at approximately 100 per cent power ranged from .03 MR/HR to 6.0 MR/HR.

The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed.

The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Determination of temperature sensing element and instrumentation drifts could not be made due to a lack of comparative data. Five temperature intercalibrations were performed using the calibrating Tc resistance thermometers as a standard. The data obtained from the nuclear instrumentation was too erratic to form any conclusions.

The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Of the 62 core thermocouples observed 19 were either reading less than 400 F or were reading in excess of 20 F from the calibrating thermometer temperatures. In each case the thermocouple was considered defective. The remainder were within 2 per cent of the calibrating thermometers. The primary loop (Norwood Indicators) resistance thermometers all read with 0.2 percent of the calibrating thermometers. No conclusion could be made for the pressurizer temperature instruments or the boiler Tb resistance thermometers, except that the 1A boiler temperature varied 10 F to 20 F from the 1Band 1C boiler temperatures. A laboratory calibration of this instrument will be made. The data obtained from the source range nuclear instrumentation was too erratic to form any conclusion. No drift evaluation on …

The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions were the Auxiliary Chamber and the limited access areas between the containers. The highest radiation level obtained in the survey was >2500 MR/HR at the reactor chamber walkway.

The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air in the control air line nearest the reactor chamber.

The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.

The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.

The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.

In this technical report, firstly, the transfer function of a non-regenerative, base-driven transistor circuit is derived by applying the linear equivalent circuit method. The results are experimentally verified. Secondly, the idea of the inverse-gain-bandwidth is introduced as the criterion of the dynamic design. Thirdly, the stability factor is explained. Finally, it is shown that a system constructed by various types of transistor switching circuits is reduced to a long train of unit chains formed by delay units and wave-shapers, and the maximum allowable number of delay units in a unit chain is discussed. The results given here are consistent with the design procedures for transistor switching circuits established in the Digital Computer Laboratory, i.e., the emitter-follower logical circuits associated with restorers and flip flops.

The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power increase, the radiation increase was normal with no signs of bursts or peaks of radiation which would indication the failure of a blanket fuel element.

This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.

The PWR Plant was operated at approximately 60 MW net electrical output for a total of 1000 EFPH from February 3, 1959 to March 28, 1959. During this period, while performing DL-S-225, there were two planned shutdowns, no safety shutdowns or safety insertions and one flux title. The performance of the plant was satisfactory during the period of the test.