This report consists of an outline for a program for testing the air-supplied face masks currently being used as protection against P-10 atmospheres at HAPO. The test procedures which follow are intended to determine circumstances under which the mask ceases to offer protection to the wearer. To keep the scope of the test program to a minimum and also to facilitate interpretation of the findings in the light of P-10 atmospheres, the test conditions chosen were those which would be most unfavorable for the mask from a protection standpoint.

The metabolism of C{sup 14} labeled glycolic acid by Scenedesmus has been studied using radiochromatographic techniques for the separation and identification of products. When the pH of the medium was 2.8, appreciable assimilation occurred. The products were identical to those observed in C{sup 14}O{sub 2} photosynthesis. A major reaction anaerobically in the dark resulted in incorporation of C{sup 14} in almost equal amounts in the glycine and serine reservoirs. When the algae were illuminated, a diminution in the amount of glycine was observed.

Research on polonium chemistry and physics is being continued on a reduced scale. Those problems which have direct bearing on the preparation of the metal and those which will lead to a better understanding of any phenomenon encountered are being continued. Data from the calorimetric measurements of polonium on Calorimeters 39 and 46 were treated by the method of least squares to give a grand mean half life of polonium equal to 138.3993 {+-} 0.0093 days (1-13). New apparatus has been constructed for the measurement of the vapor pressure of polonium and its compounds in the low and the high temperature ranges. Technical difficulties have delayed the actual collection of data (1-22). The constant current magnet to be used for the measurement of the Hall effect of polonium has been tested and found satisfactory. A device utilizing nuclear magnetic resonance absorption for determining field strength has been constructed on a preliminary basis (1-24). A total of 208 lines in the ultraviolet region between 3200 A and 1900 A have been measured with an error of less than {+-}0.02 A (1-28). Studies on the X-ray and spark spectra of polonium and its compounds have been conducted. A preliminary study by X-ray …

Pre-operation safety studies for the Homogeneous Reactor Experiment are discussed. (C.H.)

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Static overpressure and dynamic pressure versus time over surfaces processing different physical properties were measured on two tower shots, 6 and 12. On Shot 12, three surfaces were provided: the natural desert, a water surface consisting of a flooded area, and an asphalt surface. On Shot 6, desert and asphalt areas only were available. There were 123 channels of instrumentation installed for Shot 12, and 24 for Shot 6. From the data, a system of wave-form classification was devised for overpressure and dynamic-pressure- versus-time measurements. Incorporation of this system into data analysios indicates that it is possible for an ideal peak pressure to be identified with a nonideal wave form. Introducing both variables, wave form and peak pressure, into analyses reduces ambiguioties associoated with comparing results of different nuclear tests. The data show the effect of the nature of the surface upon airblast phenomena from a nuclear explosion. The effects of surface conditions upon shock phenomena are made more understandable by a review of temperature computatioons, using shock wave parameters in addition to an analysis based upon the arrioval time of the thermal pulse. A phenomenological discussion of precursor formation is presented, and comparisons are made using data from all …

Non-symmetrical main coolant system analysis is an IBM-704 digital program for calculating the reactor generation, primary coolant temperature distribution, and steam temperature, pressure, and flow to the main and auxiliary turbines during a transient period. The program represents a system composed of a two-pass high pressure water cooled reactor ivith tivo main primary coolant loops each having its own steam generator, separator, and drum. The generated steam from each loop is piped into a common header which is then piped to the main and auxiliary turbines and other steam loads in the system. The mathematical representation for solution is described. (M.H.R.)

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Heat capacity measurements of yttrium were made from 15 to 350 deg K. Lattice constants are given for rare earth-carbon systems. Thermal analyses were carried out on rare earth fluorides to determine their melting points. The extraction of fission products with silver is discussed. A study was made of the vertical distribution of both Zr and carbon in a sample of U-- Zr alloy prepared from U metal. The degree of immiscibility of U and rare earth metals was determnined, and the results are given. The solubility of Hg in organic solvents at 25 deg C is presented. (W. L.H.)

Progress is reported on: a bastnasite processing procedure; oxidation of Ce)/sup 3+/ in HNO/sub 3/; and liquid metal extraction of fission products from U. (For preceding period see ISC-836.) (T.R.H.)

Deviations from the allowed spectrum shape observed in P/sup 32/ beta - decay are discussed. Coincidence data taken on Yb/sup 169/ and Tb/sup 160/ are reviewed. The directional correlation function for the 357 to 82 kcv gamma cascade in Cs/sup 133/ following Ba/sup 133/ electron capture decay was determined. The detection of trace oxygen impuritics in metals by the beta activity from x-ray bombardment appears feasible. Results obtained in tests of this mcthod are reported. A pulse heating method for measuring the high- temperature specific heats of metals was developed and applied to Fe in the temperature range 25 to 1000 deg C. The results of electrical resistivity measurements made on Ni and Ni-alloys at temperatures between 25 and 1000 deg C are plotted. Discussions of the semiconducting properties of Mg/sub 2/Si and Mg/ sub 2/Ge single crystals are included. (For preceding period see ISC-833.) (D.E.B.)

Following HRT runs 13 and 14, several metallic specimens were removed from the high pressure system and transferred to the Materials Section for examination. Samples of scale accumulation in the high pressure system were also taken after these runs and transferred to the Materials Section. Examination and analyses of these several specimens are still in progress, but some of the results are available and are reported. A possible interpretation of some of these results indicates that a considerable quantity of nickel was contained in the core scale accumulation at the end of run 13, and that part of this nicke1 was dissolved in solution during run 14. The amount of nickel which may have come from this source during run 14 roughly accounts for all of the increase in nickel in solution durirg run 14. A significant amount of uranium was also found in the sca1e accunnulation in the core after run 13. (auth)

The comparison is made on the basis of nuclear requirements, properties, cost, and performance under irradiation. Results of published work were reviewed on the effects of irradiation on beryllium oxide and beryllium oxide - uranium dioxide dispersions. A research proposal for a Maritime Gas-cooled Reaotor Moderator is included. (J.R.D.)

Side-to-side flux distributions calculated for ``rods out`` operation are compared to the normal equilibrium distributions. The results are highly sensitive to enrichment and flattening unbalance. Near side tube power limits are reached at total pile powers as low as 39%, and as high as 85% of the normal equilibrium. power. Calculations indicate that, with the current loading patterns, B, D, DR, F, H, and KW, theoretically could make rods out scram recoveries without exceeding tube power limits, whereas C and KE could not. Longitudinal flux profiles corresponding to possible control rod and mixing piece configurations are compared to the ideal cosine distribution. Peak fluxes for a given column power vary from 86 to 111 % of a cosine maximum. The position of the maximum flux varies from 115 cm (5.1 slugs) downstream to 131 cm (5.8 slugs) upstream of the center line of the slug column. The effects of non-uniform (front-to-rear) enrichment and flattening charges are not considered.

Order-disorder structures of Fe--Al alloys were studied and data on the Muller indices for the diffracting planes of the lattices in the random distribution of FeAl, and Fe/sub 2/Al structures are given. X-ray data for mechanical properties correlation with order-disorder transformation in alloys are tabulated listing the reflecting planes for the various super lattice structures, interplanar spacings, and Bragg angles. Also included are data on x- ray-crystal analyses as function of various heat treatments, and tabulated data on tensile testing. (J.R.D.)

As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating reagents. The remaining contamination (10/sup 4/ - 10/ sup 5/ d/-m/100 sq cm) was fixed to the surface with three coats of paint. The general beta-gamma radiation background was decreased from 2000 to 30 mr/hr and the long-lived alpha contamination in the air was reduced from 2 x 10/sup -10/ to 8 x 10/sup -13/ mu c/cc. Approximately 141 g of plutonium was flushed from the cell surfaces. The total direct effort expended was 3000 man-hr including 250 entries into the cell, 175 of which were made in plastic air suits. There were no overexposares from beta-gamma radiation and no detectable increase in the body burden of plutonium of any individual involved. (auth)

The homogeneous decomposition of H/sub 2/O/sub 2/ by HNO/sub 3/, and by HNO/sub 3/ solutions (>1M) containing Pu(IV); Pu(IV) and Pt; Pu(IV) with Cu(II) and Fe(III); and Pu(IV) with Pt, Cu(II), and Fe(III) as a function of temperature is investigated. The range of STAH/sub 2/O/sub 2/! is 10/sup -2/ to 10/sup -1/M, and STAPu(IV)! p 1.25M. The evolution of gas is first order in all cases up to STAHNO/sub 3/! approximately 10M. Above STAHNO/sub 3/! approximately 10M, the reaction is no longer first order. Approximate activation energies for the decomposition of H/sub 2/O/sub 2/ by the various catalysts are listed. (auth)

The C reactor is presently, operating with all process water discharging through one downcomer. Pressure measurements at the downcomer lid show the top tray is nearly flooded, thus prohibiting further flow increases until the downcomer is modified or both downcomers are used simultaneously. Operation with two downcomers can result in two sources of error in the power calculation: (1) Errors in measured outlet temperature can occur, apparently due to the increased venting capacity. The magnitude of the effect is probably unpredictable and could not be compensated for in the power calculation. Since the temperature error occurs only downstream of the downcomer vents, the logical solution is to move the outlet temperature devices to the risers. The method of administering bulk temperature limits will have to be changed to account for the thermal shield flow entering downstream of the outlet thermohms. (2) Simultaneous flow and temperature unbalances can result in power calculation errors since there is no way of knowing the actual flow through each downcomer. It is assumed that the power calculation would have to be made from the total flow and the average of the two outlet temperatures. The primary purpose of this study was to determine whether the …

A review is given of the present state of knowledge concerning the condensed phases of He{sup 3}. Attention is confined to the pure substance, and emphasis is placed upon the theoretical understanding of the material.

A feasibility study was conducted on the application of activation analysis to forensic chemistry. Test portions of automobile paint finish, soot, and soil samples were irradiated in the ORNL Graphite Reactor and the induced gamma radioactivity of each specimen measured with a gamma scintillation spectrometer. Spectral decay curves of the radionuclides in the various specimens classified the materials as to origin. This nondestructive technique is particularly suitable for the analysis of evidence samples that must be maintained in its as-is'' state. (auth)

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A computer program was written to calculate the initial ratio of isotopes which should be used in an in-core neutron flux detector to obtain the maximum use lifetime where the useful lifetime is defined as that period of time during which the sensitivity of the detector remains within specified limits. Input data for the program include cross sections of the isotopes to be used. In order that various reactor environments might be considered, Westcott cross sections have been employed. Westcott cross sections assume that the neutron spectrum in a thermal reactor can be characterized by the temperature, T, and by a spectral parameter, r. An experimental technique was developed for measuring these parameters. The evaluation of the parameter, r, is based on a standard technique comparing the relative radioactivity induced in bare and cadmium-covered cobalt samples. The determination of the neutron temperature, T, was made using a mass spectrometer to determine the isotopic changes in uranium and plutonium samples as a function of.exposure in the neutron flux. This is a new technique which appears to be both simple and accurate. The irradiations were made in a water-cooled irradiation facility located in the KE Hanford production reactor. Based on the results …