Activities in a program to obtain data on thermal-stressfatigue in various stainless steels under reactor conditions are reported. Information concerning procurement of equipment and materials is given along results of initial testing. A specimen of 304 stainless steel was strain-rate tested at 100 to 900 deg C. The averaged result of this test was 0.0005 in./in.-sec. Tensile testing of standard ASTM 1/2-in.-dia stainless steel rods is underway. Data obtained so far in the program are compared with that obtained earlier by other investigators. (J.R.D.)

This report discusses the conference on direct energy conversion.

The SNAP-7C 10-watt Sr/sup 90/ thermoelectric generator, the converter, batteries, and weather station housing that were delivered to Antarctica in December 1961 are described. Thermoelectric analysis, thermal analysis, fuel form and shielding requirements, generator assembly, electrical system, operational tests, and environmental testing are discussed. (M.C.G.)

For the radioisotopes with half-lives over a year, only eight appear to be obtainable in the foreseeable future. The fission products, strontium-90, cesium-137, and promethium-147, exist in wastes from reactor processing, diluted with enormous volumes of other elements and salts. Among those isotopes producible by irradiation of special target materials (cobalt-60, uranium-232, plutonium-238, and curium-244) cobalt-60, though easy to produce, requires a special design for the heat source generator because much of its emitted energy is penetrating gamma radiation. Cobalt-60 appears, therefore, to be rather limited in its prospects for use. Plutonium-238 is favored as a heat source because of its long half-line and no need for special shielding. However, its projected high cost, scarcity, and biological hazard encourages the search for a competitive material. When plutonium assumes a significant place as a recycled fuel in thermal reactors for power production, curium-244 can then become available at costs below that for plutonium-238. Curiunm-244 has five times the specific power of plutonium-238 and appears to be just as easy to handle. Promethium-147, although probably on the ''short end'' of the half-life scale, can be considered for some uses as a substitute for plutonium-238. Although the factors of availability, gamma activity, and …

The following analysis of the induced radioactivity in SNAP-50/SPUR electrical machinery having a high cobalt content is submitted. Induced radioactivity in the flight vehicle will contribute negligibly to allowable radiation levels. This is especially so due to the low neutron to gamma ratio of assumed radiation damage tolerances to semiconductors. A calculation to estimate the order of magnitude of induced radioactivity in cobalt is attached. The calculation is based on a best guess of the neutron spectrum directly behind a lithium hydride shield. The resulting low cobalt activity and associated dose rate of about 1 mr/hr at 10 ft from a generator or a motor is insignificant. Although the evaluation indicates insignificant levels of induced radioactivity, this conclusion is not applicable to a ground test. Neutron moderation and scattering from a containment vessel and biological shield would greatly perturb the neutron environment behind the flight shield. Posttest handling of all components within the vacuum test chamber will undoubtedly be a problem. Notwithstanding the importance of limiting induced radioactivity, other considerations such as economy, cooling and vacuum requirements will largely dictate the final facility design. In summary, an activation analysis involves the overall facility design and will not be readily resolved. …

This report covers the following titles: (1) Fertility and litter size of normally ovulated and artificially ovulated mice; (2) Further studies on sterility produced in male mice by deuterium oxide; (3) Planarian disaggregation; (4) Uptake of organic compounds by planarians. II; (5) Effects of environmental complexity and training on acetylcholinesterase and cholinesterase activity in rat brain; (6) Effects of environmental complexity and training on brain chemistry and anatomy among mature rats; (7) Improvements in paper chromatographic techniques for labeled cell extracts; (8) measurement and adjustment of pH in small volumes of solutions; (9) Carbon-14 and Nitrogen-15 tracer studies of amino acid synthesis during photosynthesis by Chlorella Pyrenoidosa; (10) Photosynthesis of {sup 14}C-labeled protein from {sup 14}CO{sub 2} by Chlorella; (11) Further studies on carboxydismutase; (12) Electron microscopy of chlorophyll a crystals; (13) The possible role of chromanyl phosphates in oxidative and photosynthetic phosphorylation; (14) Oxidation-reductions of some coenzymes; (15) Preparation of some [{sup 14}C] labeled substances: glucose-6-phosphate, fructose-6-phosphate, 6-phosphogluconic acid, pyruvic acid, and succinic acid; (16) attempt to synthesize high molecular weight polynucleotides using Schramm's purely chemical method; and (17) Optical properties of some dye-polyanion complexes.

This report covers the following titles: (1) A versatile solvent to replace phenol for the paper chromatography of radioactive intermediary metabolites; (2) Chromatography of plant lipids on alumina paper; (3) Quinone and pigment composition of chloroplasts and quantasomes from Spinacea oleracea; (4) The lipid composition of chloroplast lamellae from Spinacea oleracea; (5) Metal chelates and photochemistry of flavins; (6) Photoinduced ESR in some solutions of organic electron donors and acceptors; (7) Fluorescence of oriented dye-macromolecule complexes--Theoretical study; (8) Formation of adenine by electron irradiation of methane, ammonia, and water; (9) Uptake of organic compounds by planarians; (10) The planaria: Absorption spectrum, cell disaggregation, and studies on homogenates.

This report describes the use of a target containing polarized protons in a particle-scattering experiment. Positive pions of 246-MeV kinetic energy were scattered from the polarized protons. The parameter P that was measured is equivalent to that determined by analyzing the recoil-proton polarization in scattering from an unpolarized target. It has been measured to a higher accuracy than heretofore achieved in pion-proton scattering, at an energy and at angles inconvenient for double-scattering techniques.

The chemical potential of the brine from I.I.D. Well No. 1 was evaluated and reported in Rogers Engineering Coo, Inc. March 1962 Flow Test Report. This evaluation considered only the recovery of sodium chloride, as the prime salable product and alternately as the raw material for conversion to salable chlorine and caustic. Both cases showed low net revenue relative to the estimated capital investment required. The subsequent three month well flow test indicates continued production of a consistent type brine can be expected from this well. Based on the flow and composition data established during this test period, chemical production potential has been examined. The separation and sale of high quality potassium chloride appears attractive. Attached are sketches of each of the two production schemes considered with estimates of capital and operating costs and revenue.

This report covers the following titles: (1) The Effects of 8-Methyl Lipoic Acid on the Evolution of Oxygen and Reduction of Carbon Dioxide during Photosynthesis; (2) Further {sup 14}C and {sup 15}N Tracer Studies of Amino Acid Synthesis during Photosynthesis by Chlorella Pyrenoidosa; (3) Two-Dimensional High Voltage, Low-Temperature Paper Electrophoresis of {sup 14}C-Labeled Products of Photosynthesis with {sup 14}CO{sub 2}; (4) A Search for Enzymic and Nonenzymic Reactions Between Thiamine Derivatives and Sugar Phosphates; (5) The Cytochrome Content of Purified Spinach Chloroplast Lamellae; (6) The Osmium Tetroxide Fixation of Chloroplast Lamellae; (7) Kinetics of Exoenzymes and Applications to the Determination of the Sequence of Nucleic Acids; (8) Brain Biochemistry and Behavior in Rats; (9) Experiments on Classical Conditioning and Light Habituation in Planarians; (10) Operant Conditioning in Planarians; (11) Manganese Porphyrin Complexes; (12) EPR Studies of Some Complex Organic Solutions; (13) Transient Response of Light-induced Photosynthetic Electron Paramagnetic Resonance Signals: Rhodospirillum rubrum Chromatophores; (14) Studies of the Tautomerism of Amides; (15) Structure and Mechanism of Hydrolysis of the Product of Reaction of PZ05 and Ethyl Ether; (16) A Study of the Irradiation Products of Several Nitrones; (17) Biosynthesis of the Opium Alkaloids; (18) Synthesis of methyl-{beta}-D-thiogalactoside-{sup 35}S; (19) Effect of …

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This report addresses the chemical characterization of selected core samples from the vicinity of Tatum Salt Dome, Lamar County, Mississippi.

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The Irradiated Rupture Prototype (IRP) has been used for rupture testing irradiated NPR prototype fuel elements. Most of the tests have been made to determine the rupture effect of different reactor exposures, fuel element geometries and water cooldown rates following the start of the rupture. This report summarizes the results obtained to date, mentions where information is lacking and gives further tests scheduled for the IRP.

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Two techniques for the end-of-life shutdown of orbiting SNAP reactors are presented. One technique consists of two alternative methods for the destruction of the reactor core. This technique (and others) have been investigated during the past year. A second technique, uses a naturally occurring phenomena, which works on the principle of a low neutron absorbing nuclide decaying to a high neutron absorbing daughter (poison). The present design criteria for the latter technique is that only a small reduction in reactivity should occur during the mission lifetime with the slow build-up of poison eventually shutting down the reactor at some later date. Tritium, an isotope of hydrogen is presented as a parent that appears to meet all of the requirements for such an end-of-life shutdown device. The daughter, He/sup 3/ has a high neutron absorption cross section. The results of a preliminary study of the tritium device are presented.

Estimates are made relating radionuclide movement to ground water velocity as part of the safety program for a proposed experiment to detonate nuclear devices within the Tatum salt dome. The estimates are based on distribution coefficients obtained from laboratory studies. Core samples obtained from hydrologic test well HT-3, Tatum salt dome, Lamar County, Mississippi, were equilibrated with radionuclides in solutions simulating aquifer waters found in the area. The combinations of Cenozoic sand and silty clay, and quality of water of the area were studied and summarized. The distribution coefficients obtained for different radionuclides were tested and indicate retardation factors from 1.3 to 857 for the travel time of these radionuclides when compared to the travel time of water in the aquifer system. Laboratory results indicate that migration of any radioisotope inadvertently introduced to the aquifers in the vicinity of the dome as a result of proposed nuclear test explosions would be extremely slow. Revised estimates of the rate of dissolved radioisotope movement will be made on the basis of further laboratory studies utilizing chromatographic adsorption columns of 0.5 to 4.0 feet in length.

The instructions described in this procedure are typical of the operation of Test Cell A relative to the KIWI-B4A. Operation of Test Cell A relative to the NRX reactor will require modifications dictated by specific test requirements. Under NRX conditions, it will be the responsibility of the test cell manager to evaluate the capabilities of Test Cell A in terms of given test requirements and then set forth detailed checklists which will be compatible with the test requirements.

This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and purification of Np/sup 237/ and Pu/sup 238/, the finishing of Np, the preparation of NpO/sub 2/, the disposal of spent resin, and the safety aspects of the handling of hydrazine. The section on the fabrication of NpO/sub 2/-Al slugs will be added later. 76 refs., 22 figs.

This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1962. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1962. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1962. Tables list the major disposal sites in the separation facilities, total volume of waste discharged to each location, and the gross amounts of plutonium and beta particle emitters discharged to ground since startup. This same data is presented on a monthly basis for cribs still in use. Information is presented on the source of the waste stream and the settling facility if used. Isotopic data are included for disposal sites from which the waste was analyzed for specific contaminants. Estimates of contamination and volumes discharged to swamps are also included.

On September 13 and 14, 1962, 8.3 curies of iodine-131 were emitted from the Hanford Redox Plant at a rate of from 0.35 to 0.65 curies per hour for a period of approximately 18 hours. During the emission, the plume trajectories were plotted from meteorological data and samples were collected across the predicted plume trajectories at several altitudes and at distances up to 50 miles from the Plant. Filter, charcoal trap, and air samples were collected during the emission using aircraft; and caustic scrubber, vegetation, and milk samples were collected during and after the emission at selected ground stations in the usual manner. Appropriate background samples were collected before the test began. The data and conclusions are given in this report.

This document details activities of the N-Reactor Department during the month of October 1963.

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.