The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)

An estimate was made of the fission product activity which would result in the HFIR primary coolant system following a meltdown of the fuel element within the reactor. The rare gases and the halogens appear to be the main contributors to the gamma activity in the coolant system imnmediately after the meltdown, and iodine appears to be the main contributor 24 hours after the meltdown. (auth)

This report is about the Advantages of Glass Micro-balloons as Filler Material

The computer program which performs spatial reconstruction of events photographed in a bubble chamber is required to eliminate human and digitizer errors. It recognizes and corrects for single nuclear scatterings in the presence of multiple Coulomb scatterings. Momentum components are determined and kinematic constraints are applied. Measured parameters are performed into special reference frames and quantities of physical interest are calculated. Results are stored in a tape file containing all events of one reaction type.

The design, development, and operation of metaldiaphragm service pumps for aqueous homogeneous reactojs are discussed. It is shown that with proper design and materials selection, the dlaphragm heads and check valves can operate continuously for about two years. (C.J.G.)

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.

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)

Losses of fertile and fissile materials during chemical decladding of irradiated prototype Consolidated Edison power-reactor fuel pins by the Sulfex and Darex processes were determined, on a laboratory scale, in all-glass apparatus. For air-fired low-density (-85 per cent of theoretical) fuel cores, minimum losses of uranium, thorium, and plutonium were in the 0.1 to 0.2 per cent range, by either process. These losses increased if the dejacketed cores were allowed to remain in contact with the cladding solution. No selectivity of dissolution of core components was apparent. Comparable losses were obtained with similar unirradiated fuel pins, irradiated core pellets showed a tendency to shatter. When shattered core pellets were present, losses to the cladding solution were excessive. Losses of from 0.5 to 4.5 per cent were observed, depending on the extent of core fragmentation and the time of contact with the cladding solution. No correlation between burnup and extent of shattering was discernible. Core dissolution times were not lengthened by irradiation to the 175 to 300-Mwd/t core level. (auth)

The theory of mass transfer into a flowing fluid is utilizes to estimate the effect of gas film resistance on overall rates of transfer through a porous septum. The expressions developed for the mass transfer ratio...

The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.

In efforts to improve the neutron economy and lower the capital costs of sodium graphite reactors, several methods of separating the sodium and graphite were investigated including the calandria, the thimble, and the canned moderator reactors. An analysis including nuclear, heat transfer, and economic comparisons was made of these SGR concepts. Based upon neutron economy and feasibility of core fabrication, the calandria concept appears to offer the greatest potential for improvement in 8GR design. The thimble concept provides some improvement in neutron economy but introduced numerous problems requiring developmental work. (auth)

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)

Tantalum fabrication methods primarily for use as a container for molten plutonium are described. One method involved the rolling of a Ta billet into sheet of the desired age, cutting a circular blank, and deep drawing the tantalum blank through successive stages into the desimed shape. Another method used for the fabrication of Ta containers consisted of a combination of impact extrusion and ironing. This method involved the extrusion of the cast billet into rod, swaging the rod to a suitable diameter, and cutting it into slugs of the desired length. The slugs were then impact rod, swaging the rid ti a suitable diameter, and cutting it into slugs of the desired length. The slugs were then impact extruded into heavy walled containers. These starting containers were then taken through successive dies where the wall thickness was ironed down to the desired gage. (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.)

Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.

Moderator Reactor (VMR), a reactor concept under investigation by American-Standard for the AEC. The VMR is light-water moderated and cooled and is fueled with slightly enriched uranium dioxide pellets loaded into aluminum tubes. The core consists of 37 hexagonal fuel cans each loaded with 61 fuel pins. The cooling water, which flows upward around the pins inside the fuel can, boils in passing through the core. Reactor control in the prototype will be achieved by varying the moderator height. The site, laboratory, and the critical assembly, including control and safety mechanisms, are described in detuil. Special characteristics of the assembly pentinent to safety were calculated. The nuclesr energy released and the average and maximum fuel temperatures resulting from step reactivity increases up to 2% DELTA k/k are presented graphically for two cases. In the first case, fuel-temperature effects are considered to be the oniy shutdown mechanism; in the second radiolytic gas is considered to contribute to shutdown, in addition to fuel-temperature effects. The accident considered to be the maximum credible accident causes a step addition in reactivity of 1.5% DELTA k/k. The nuclear-energy release is between 160 and 310 megawatt-sec depending on the assumed shutdown mechanisms. This accident does not …

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)

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.

Monthly report documenting Imperial Sugar operational expenses for the year, broken down by actual sales and production, with estimated operational numbers for the remainder of the year.

Sugar Stock and Sales report for Imperial Sugar Company including a list of sugar sales for the date showing the amounts and estimated balance separated by location, raw sugar, and refined sugar sales.

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

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.

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)