For presentation at the American Chemical Society's Nuclear Technology Symposium, Boston, Apr. 5-10, Information is presented from studies with materials and conditions simulating those expected in anm aqueous homogeneous reactor for the formation of insoluble corrosion and fission products in aqueous UO/sub 2/ SO/sub 4/ solutions used as a reactor fuel. Sulfate salts which become insoluble as the temperature inereases deposited preferentially and reversibly on hot walls. Oxides from hydrolysis of sulfate salts deposit on any surfaces while insoluble corrosion products released into the solution show variable degrees of circulation. (auth)

As part of the over-all program of investigation of the rheological properties of aqueous thorium oxide slurries, a capillary-tube viscometer was designed for routine determiation of shear diagrams of slurries over a temperature range of 30 to 85 deg C. A particular feature of this viscometer is the vertical oricntation of the capillary tube which minimizes the effect on the results obtained with dilate, rapidly settling slurries. (auth)

The head-end system for the ARE salt was tested with barren salt and shown to be operable. Transfer of the final batch of salt by gravity flow from the bold tank was shown to be feasible with a redesigned feed salt freeze valve. The CRP trap was also redesigned but the remote dumping mechanism did not function properly. (auth)

None

Various heat transfer mechanisms which have been previously proposed are analyzed in the light of recent experiments. Evidence is presented in favor of a liquid-vapor exchange mechanism and against the widely accepted "micro-convection" mechanism. The vapor-liquid exchange rnechanism is shown to explain the insensltivity of boiling heat flux to the level of subcooling. A "Reynolds Analogy" for nucleate boiling is presented in some detail. A procedure is given for calculating the superheat at which the liquid bulk velocity ceases to contribute to the heat flux. An expression for the growth of a vapor bubble in a highly superheated liquid is deduced. A method is presented which allows the deduction of correlations for nucleate boiling which give the dependence of heat flux on superheat and system pressure. Two such correlations are presented and results are compared with experiment. It is shown that one correlation yields the heat flux for different liquids varying from water to mercury, without necessitating any change in constant or exponent of the correlation. (auth)

An investigation of trim from the HRP Dump Valve Test Loop revealed that performance improved with increasing poppet hardness. From this it was hypothesized that deformation of softer poppets increased the poppet-seat contact area, thus reducing the closing pressure. The deformation areas of a number of poppets were measured and the closing pressures calculated. A plot of closing pressure against leak rate showed a fair correlation and tends to support the hypothesis. (auth)

A three-stage mass spectrometer that utilizes two consecutive magnetic focusing;lenses of 20-in. radii followed by a 20-in. radius-of-curvature electrostatic analyzer is described. An abundance sensitivity of 1010 was measurcd for this instrument in the low mass region. Application of this instrument to analytical and research problems in the field of mass spectrometry and the results obtained are discussed. (auth)

The accuracy with which the breeding ratio of HRE-3 could be determined after a period of reactor operation was investigated. Inaccuracies in measurement of the core U/sup 233/ inventory and blanket U/sup 233/ and Pa/sup 233/ inventories appear to be the major sources of error. Appreciable errors could result from attempting to determine these inventories by sampling the reactor contents. For example, if generalized attack on stainless steel is at a rate of 1.0 mpy and if the associated film of corrosion products is 1% uranium, failure to account for this fuel in evaluation of the core inventory would cause an error of about 5% in the breeding ratio. (auth)

An analysis of the temperature structure in the CCR-2 fuel elements and coolant stream at the position where the maximum fuel element surface temperature exists is presented. Results were obtained by numerical methods on the IBM 704 digital computer. The effect of variation in channel size is shown, and a method of data correlation is suggested. Preliminary conclusions are presented as to the effect of temperature structure on the design and testing of gas cooled reactor fuel element configurations. In view of the rate at which gas cooled reactor work is proceeding results of the calculations are being published in their current incomplete form. The study is continuing in an effort to refine the calculations, and experimental data will eventually be available with which to verify the analytical conclusions. (auth)

Program F/sub 3/ provides an anslysts of a three group, one-dimensionni reactor in multi-region slab or cylindrical geometry. Input consists of a description of the geometry of the assembly, energy group constants defining the nuclear characteristics of each region, and control information specifying the type of calculation desired. The fission density and neutron flux, computed at each lattice point, are used to calculate the reactivity of the system. (auth)

The reduction in HRE-3 breeding ratio resulting from neutron absorptions in the core-inlet line was examined for spherical and cylindrical cores; it was found to be less than 0.5% if the pipe does not extend more than 1/4 the way from the top to the bottom of the core. The power density at the end of the pipe would be 57 kw/l if it extended 5 in. into the sphere. (auth)

The study of interactions and decay of K mesons continued, using the 10- inch liquid hydrogen bubble chamber and emulsions. Four emulsion stacks were exposed for two internal groups and twenty-three stacks were exposed for seventeen groups from outside the Laboratory. Interactions of pi /sup -/ mesons were observed with a 30-inch propane bubble chamber and with emulsions. Ten emulsion stacks were exposed to neutral-particle beams and one stack to the internal 6.2-Bev proton beam. The 30-inch propane bubble chamber and emulsions were used to study the interactions of antiprotons. Eighteen target bombardments in the internal proton beam were made for the chemistry group. Successful tests were completed of two static-electromagnetic velocity spectrometers for the separation of highenergy particles. One was of coaxial construction, the other of parallel-plate construction. (For preceding period see UCRL-6114.) (auth)

Somewhere in the future lies the possibility that the existing HAPO reactors will no longer be required for the production of weapons grade plutonium. This could come about either through advances in technology or through changes in the requirements for this particular fissionable isotope as a weapons material. In any event, should these reactors no longer be utilized for plutonium production, it would be appropriate to consider the possibility of their conversion to other uses, notably that of electrical power production. Accordingly, this study has been made with the objective of investigating the economic and technological feasibility of such conversion. However, it must be recognized that the results presented herein are based on present day technology and economic philosophy and that within the next five years we may experience considerable renovation of these criteria which could alter the conclusions of the study appreciably. The primary benefit to be gained from this preliminary study is to narrow the area of future and more detailed investigation as much as possible so that if and when such a conversion appears likely, a significant fraction of the almost infinite number of combinations of reactor and power plant parameters may be rejected at the outset.

A new method of introducing predetermined quantities of hydrogen into zirconium was developed and evaluated. The procedure is simple, effective, and inherently good in preverting oxygen and nitrogen contamination. Zirconium samples containing four levels of dissolved hydrogenated to 100, 300, 3500, and 7700 ppm hydrogen. Dissolved oxygen was found to decrease hydrogen absorption in both the alpha and beta modifications of zirconium. The effect of hydrogen on density, hardness, and microstructure was determined. X-ray-diffraction measurements were also obtained. (auth)

The thenoyltrifluoroacetone (TTA) extraction method has been investigated for the determination of microgram concentrations of thorium in uranium ores and concertrates. The tolerance limits for eighteen elements commonly found in uranium ore concentrates were established. The effect of phosphate on estraction of thorium was studied. Cobalt, copper, tin, and bismuth were found to seriously interfere with the Thoron method for the determination of thorium after a TTA extraction. A TTA extraction method is described for the separation of thorium and uranium from the interfering ions, employing preliminary acid sulfide and ammonium hydroxide separations. The method is rapid, and results obtained compare favorably with results obtained with other procedures. (auth)

The results of an experimental investigation of heat transfer to a high velocity, vortex air flow are presented. Heat-transfer coefficients have been observed for vortex flow in tubes which are larger thaa those for linear turbulent flow at a given flow power dlssipation per unit surface area. Comparisons are drawn between air in free- and forced-vortec flow within tubes having length-to-diameter ratios of 11.7 and 20.0, respectively. and linear turbulent flow in identical tubes. For the observed range of flow power disslpation, the freevortex flow system is characterized by a heat-transfer coefficieut one to two hundred per cent larger than that calculated for linear turbuleut flow at the same pumping power. The forced-vortex flow system exhibits a superiority over linear flow only at high flow powers. (auth)

None

A compilation of available data on the spectra of thorium is presented, including energy levels and classified lines with Zeeman effects and isotope shifts, as well as certain data on unclassified lines. The present status of knowledge of these spectra is discussed. (auth)

The electical analog study of the diaphragm feed pump system resulted in changes to the system which have improved the over-all operation and reliability of the pumps. Specifically, the study showed that if the release of the high- pressure oil from the pulsator through the valve on the Scott and Williams pump could be made to take place over a longer period of time, pressure oscillations could be substantially reduced. Also, pressure surges could be reduced by placing an accumulator in the pump discharge line near the check valve. Both of these have been incorporated into sulted in a quieter and smoother operation of the pumping system. (auth)

From the standpoint of erosion, a long dump line may be preferable to a throttling dump valve to achieve the pressure drop from the HRE-3 slurry blanket to the dump tank. Extended length HRE-3 dump lines in which the maximum average velocity is 20 fps, the smallest allowable line size is 1/2 in., and the time for dumping is 10 minutes are investigated. Twenty-six parallel 1/2-in. Sch. 80 pipes, each 725 ft long, or four parallel 1 1/2-in. Sch. 80 pipes each 2,000 ft long are required. To avoid localized velocities considerably higher than 20 fps as a result ef flashing, these pipes can be submerged in a 25,000 gal pool of water initially at 135 deg F and with 40 deg F allowable temperature rise. It can be concluded that if the velocity, line size, and dumping time are limited to the values listed above, use of restrictor piping to achieve the pressure drop is not very practical. If higher velocities and flashing are allowed, a cursory study indicates that for an average velocity in the range from 100 to 200 fps, one 1 1/4-in. (or smaller) line of less than 250-ft length could be used. Flashing would occur, …

The separations plants operated on schedule, and Pu production exceeded commitment. UO{sub 3} production and shipments were also ahead of schedule. Purex operation under pseudo two-cycle conditions (elimination of HS and 1A columns, co-decontamination cycle concentrator HCP) was successful. Final U stream was 3{times} lower in Pu than ever before; {gamma} activity in recovered HNO{sub 3} was also low. Four of 6 special E metal batches were processed through Redox and analyzed. Boric acid is removed from solvent extraction process via aq waste. The filter in Task II hydrofluorinator was changed from carbon to Poroloy. Various modifications to equipment were made.

None

The reactivities of several U--Nb-- Zr alloys in the Sodium Reactcr Experiment are compared with that of 2.8% enriched U fuel. The alloys considered have the following compositions: 15% Nb--70% U--15% Zr; 12% Nb--82% U--6% Zr; and 6% Nb--82% U-- 12% Zr. Each alloy is studied at U enrichments of 3, 7, and 11%, and the alloy enrichments necessary to give the same reactivity as the 2.8% enriched U fuel are found by interpolation. (T.F.H.)

The recent Windscale incident has emphasized the need for available light aircraft and proper instrumentation for aerial surveys following a release of large quantities of airborne radioactive materials. Early tests (1951 and 1955) are reviewed, and the program now in effect at the Oak Ridge National Laboratory is presented. (auth)