An envelope-type microstructure produced by liquidphase sintering techniques was used to develop ductiIe molybdenum-base alloys for sodium-cooled fast reactor application. A total of 105 compositions was examined; 21 showed evidence of room-temperature ductility, and a number of other compositions appeared promising. The prerequisites for obtaining ductile liquid-phase sintered materials were demonstrated. The most ductile alloys produced are based on the Mo--Pd--Cu and Mo --W--Ni--Fe systems. Molybdenum-base compositions were developed which could be rolled to 90% reduction in thickness at room temperature. The compactibility of selected alloys with uranium at 750 deg C and liquid sodium at 650 deg C was studied. In both cases the presence of iron and nickel was found to be deleterious. Although alloys compatible with uranium were produced, the specimens exposed to liquid sodium all showed evidence of attack to varying degrees. Two compositions based on the Mo--W--Ni and W--Cr--Ni systems, respectively, appear to hold promise as potential canning materials for sodium- cooled fast reactor application. (auth)

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses experimentation with fabrication to improve thermal stability of tested combinations by further alloying.

Cavitational flow has been known to exist in-rear crossheader ``Parker`` fittings at B, D, and F Reactors for the last five or six years. Calculations showing initiation of cavitational flow as a result of high flow rates in the present fittings were verified by experimental data in 1954. A study is currently being conducted to determine the required plant modifications to obtain flow increases on the order of fifty percent above existing flows. This study and the results of preliminary tests that show nominal flow increases may be obtained by reaming rear crossheader fittings has focused attention on the condition of existing rear face piping. To obtain an estimate of the effect of cavitation in rear crossheader fittings resulting from past and current operating conditions, twenty one fittings were examined during the period October 6, 1959 to November 30, 1959. This document reports the inspection results.

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Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Highway Department may provide in its bridge improvement contracts that the contractor may keep the portions of a dismantled bridge not needed by the Department, or whether such materials must be disposed of under Article 666 pertaining to the Board of Control.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Liability of State for Attorneys' Fees in Condemnation Suits by Counties.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Will it be mandatory that the words "State Archives and Library Building" be placed in permanent form on that Building that will house the Texas State Library?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Under the provisions of Article 4075b, V.A.C.S., as amended, is the Game and Fish Commission required to issue a Commercial Bay-Bait Shrimp Boat license to any person who, for a valid reason, was unable or failed to make application during the months of January & February?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Method of disposing of cigarettes seized by Comptroller's Department under provisions of Chapter 7, H.B. 11, 56th Leg., 3rd C.S.

From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.

Discussions held with A. S. Stetson, General George Gordes and W. Compton going over technical aspects of Contract NO-S-935 for the research and development studies on coating materials for SNAP reactors.

Abstract. Fourteen commercial enamel frits from five different manufacturers were tested to determine their abilities to protect Nb-1% Zr during the forging cycle in the temperature range of 1800 to 2300 deg F. One frit was found to afford good coverage and protection at 2200 deg F at times up to 5 hours of exposure. Adherence was excellent during upset forging of a coated Nb--1% Zr sample heated 45 minutes at 2200 deg F. Another frit afforded good protection and coverage at 1700 deg F. (auth)

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BS>A test was performed to determine the activity build-up inside the 1AC and 1BD purification demineralizer concrete enclosure. A maximum radiation level of 1100 mr/hr was detected inside the 1AC demineralizer enclosure at a point 10.0 ft from the top. The maximum radiation level inside the 1BD enclosure was 700 mr/hr at a point 9.5 ft below the top. An analysis of data from five tests indicates that the extent of the activity build-up, as well as the level of activity, is definitely increasing. (W.L.H.)

A hot-pressing system was designed and is adaptable for bomb melting experiments up to 2000 deg C. Two devices were constructed for measuring. One was designed to measure Seebeck coefficients, resistivities, and bond resistances of swaged and machined thermoelectric wafers and the other was designed to measure thermoelectric parameters of cylindrical thermoelectric pellets up to 1000 deg C. Design studies on a fission-fired thermoelectric generator were completed. Seebeck coefficient and resistivity were determined for Li/sub .06/Ni/ sub .94/ and p type PbTe as a function of thermal fiux at 400 deg C (average). Designs of prototype thermonuclear fuel elements are presented which include single-leg, double-leg, multi-junction notched-bar, and multi-junction pelletized designs. The effects of heattreatment on the thermoelectric properties of n and p type PbTe were determined at 68 deg F. The compatibility of PbTe and GeTe with cladding materials was investigated at 510, 600, and 650 deg C. The results of life testing a swaged single-leg GeTe element are discussed. The nuclear characteristics of a 500-kw thermoelectric core that employs a rod-type fuel element were calculated. Designs of a thermoelectric reactor system that utilizes thermal circulation are presented. (For preceding period see WCAP- 1545.) (C.J.G.)

Additional work on the synthesis and fabrication of uranium nitride produced an improved product free of oxide contamination as indicated by x-ray analysis. Further work to increase the density of the sintered pellets is needed. A stock of several pounds of stoichiometric uranium monocarbide was prepared by carbon reduction of uranium dioxide. Pellets having bulk densities ranging from 93 to 96% theoretical were obtained by cold pressing and sfntering. Initial experiments on the fabrication of bars, 3 by 1/2 by 1/4 in., by cold pressing and sintering, resulted in sound but somewhat low-density bodies. A few experiments were conducted on the production of uranium monocarbide from ammonium diuranate. The results indicate that considerable addftional work may be necessary to consistently produce a stoichiometric product. The simultaneous synthesis ard hot pressing of uranium monocarbide was funther studied and pellets with balk densities as high as 96.6% theoretical (based on 100% UC) were produced. However, metallographic examination disclosed the presence of some free uranium metal in all pellets. The synthesis of 1-lb batches of U/sub 3/Si/sub 2/ of improved quality was successfully carried out by a nonquench method. Using the U/ sub 3/Si/sub 2/ so produced, sound pellets with bulk densities up …

Micron-sized plutonium powder was produced by hydriding massive metal, then grinding and decomposing the hydride. An apparatus containing clean plutonium metal was evacuated to a pressure of 10 mu . Dry oxygen-free hydrogen was introduced and the apparatus placed in a furnace. After the reaction started, the apparatus was removed from the furnace and hydrogen added until the reaction was complete. The hydride was decomposed by heating to 400 deg C. Plutonium metal produced in this manner was porous. (C.J.G.)

The radiation level of all permanently installed mom-tored points in the Hadioactive Waste Disposal Plant was determined periodically, and the effectiveness of shielding facilities in working areas at times during which the radiation level was above limits set up by Health Physics was checked. The radiation level in all areas surveyed was less than 5 mr/hr, which is the Health Physics' limitation for the Radioactive Waste Disposal Area. Any area with a level abeve 5 mr/hr is a controlled access area posted with warning signs. (auth)

A prototype of the two-coolant-region pump shaft freezeseals intended for application to the Hallam Power Reactor sodium pumps was fabricated. Tests under simulated reactor service conditions revealed satisfactory operation only when the lower of the two regions received heat from the circulating fluid (tetralin in the tests). With the inlet temperature of tetralin to the upper region of the seal maintained at 95 deg F and that to the lower region held in the range 240 to 285 deg F the sealfunctioned satisfactorily for 1100 hr. When 95 deg F coolant was circulated through both sections of the seal excessive cooling occurred, resulting in either improper formation of the seal or in seizure of the shaft when rotative speed was low. In this case, the cooling load on the seal varied directly with both shaft speed and bulk sodium temperature. A maximum cooling load of 2.56 kw occurred at a shaft speed of 840 rpm and with a bulk sodium temperature of 1000 deg F. (C.J.G.)

Flux excursions in the HFIR and the response of its safety system have been examined for the situations arising from voids swept into the flux trap with the cooling water. It was found that by limiting the addition of void reactivity to 00 or less, temperature coefficients alone can handle the excursion without damage to the core. Curves are given which show the safety system response necessary for larger additions of void reactivity. (auth)

A method for the preparation of high-density ThO/sub 2/ of the correct particle size for vibratory compaction is under development. The method being developed appears easily adaptable to remote operation. Pure ThO/sub 2/ made by this method was readily compacted to 86% of theoretical density by pneumatic vibration. Preparations of high-density mixed ThO/sub 2/ -UO/sub 2/ and UO/sub 2/ by this general method have been successfully carried out. Densification of arc-fused mixed oxide by a pneumatic vibrator compared favorably with results of tests with the same oxide using electronic vibra tors at both Huntsville, Alabama, and Savannah River. In the limited tests with the electroinic vibrators at the other sites, it appeared that a saw-tooth wave shape gave greater densification than a sine wave or random noise. (auth)

Mechanical compression tests were performed on gasket test specimens machined to the cross-sectional dimensions of a stainless steel (Type 304) ring type gasket to be installed in the SM-1 reactor pressure vessel. Testing the mechanical properties of the gasket specimens under varying loads, and subsequent sectioning and inspection of specimens for adequacy of welded and brazed joints, gave the following results: (1) a penetration scheme involving five 0.070-in. diam. holes, spaced 1/4 in. center-to-center for each 6 1/2 in. belt circle span, may be made in a gasket ring without materially increasing the gasket stresses, (2) a lug may be welded to the gasket face to provide a brazed sealing support for 0.0625-in. diam. tubes and thermocouples, and (3) excellent attachments can be made by tungsten-inert gas welding of the lug to the gasket face and induction brazing of the tubes and thermocouples to the lug using Nicrobraz alloy. (auth)

Design details and test results of the jet-centrifugal mercury pump are presented. (auth)