Brillouin polyhedra for the intermetallic compounds of lithium and lead were determined using the zone theory. From these determinations, predictions and explanations of some electromagmetic and structural properties of the intermetallic compounds were made. (For Part IV see UCRL-4973.) (C.J.G.)

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The objectives of this test are to obtain a current knowledge of the H Reactor flow system characteristics under various transient conditions which have a reasonable probability of occurrence. The test data will be used to revaluate: (1) the H Reactor bulk effluent temperature limits, (2) the margin between the Ball 3X riser pressure trip settings, and (3) the quantitative adequacy of emergency flow available from the combined high tanks export system. This test will consist of two parts: (a) Measurement of the flow characteristics during transition from the primary coolant system to the secondary coolant system (190 steam driven pumps.) (b) Measurement of the adequacy of the last-ditch emergency water system (combined high tanks-export system) during a simulated primary and secondary coolant system failure.

The concept of an ideal current sheet is frequently useful in the design of electromagnets. Since a current sheet of any length can be represented by the superposition of two semi-infinite sheets, it is desirable to have tables for the magnetic field produced by a semiinfinite current sheet. The tables presented include both the magnetic field intensity and the magnetic vector potential. To use the tables it is not necessary to apply the symmetric properties of the fields. This doubles the size of the tables but greatly simplifies their use. (auth)

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Six 1.6% enriched Zircaloy-2 jacketed seven-rod cluster elements with modified end supports and one Zircaloy-2 jacketed Pu-A1 seven-rod cluster element will be irradiated in KER Loop 1 to an exposure of about 4500 MWD/T.

A tabulation (too large to be included in the memorandum) of the hypergeometric probability distribution for lot sizes up to and including 50 is described. Uses of the tabulation in sampling inspection and reliability are described. The tabulation provides a simple way of testing the equality of two proportions when the total number of observations on the proportions does not exceed 50. (auth)

The work on the hydraulic collapse or instability of flat plates was extended by considering flow redistribution and the effect of unequal friction drops in the deflected region of the channels. A general formula for the pressure distribution over a plate as a function of the plate deflection is derived. From this general formula, linearized formulas for small deflections are derived for the pressure distribution and the critical velocity. Graphs of pressure distribution for various assumed deflection curves are presented. Formulas and curves are given for the magnification of initial deflections as a function of approach to the critical velocity. (auth)

The 234-5 Building ventilation exhaust is continuously sampled for the purpose of estimating the amount of radioactive (alpha emitting) material discharged to the atmosphere. Although a record is kept of the gross amount of radioactive material discharged, few data are available concerning the size and kind of active particles in the exhaust air. Knowledge of the particle size permits: (1) an estimate of the validity of samples drawn through the sampling system, (2) a better knowledge of what the active particle ground deposition pattern might be, and (3) may provide information relating to filter performance. The kind of radioactive material discharged is important in determining relative health hazards. The object of this work was to determine the size and kind of radioactive particles in the 234-5 Building ventilation exhaust. A secondary objective was to review present routine sampling of the stream with particular regard to the particulates to be sampled.

High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooler of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory. Heat transfer calculations are compared with the experimental data and found to correlate within 10%. (auth)

This report addresses the AEC symposium on particle-fluid mechanics

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High-absorbancy spectrophotometry was applied to the precise determination of about 0.15% cobalt in aluminum by the 1-(2-pyridylazo)-2- naphthol method. The absorbancies of sample aliquots were measured versus a standard containing 50 mu g of cobalt. The relative concentration error for a single measurement, assuming a 1% transmittancy error, is 0.93% and the coefficient of variation of 5 cobalt determinations is 0.5%. (auth)

Power rate of rise measuring instrumentation is being procured for all of the Hanford piles, and a prototype installation is now in service at D reactor. This instrumentation is expected to provide valuable assistance to the pile operator during the start-up rise to operating power; in order to best utilize the instrument, procedures and limits must be determined on the basis of the relationship between the flux rate of change and the instrument response. As with any measuring instrument, there is an inherent delay in the power rate meter circuitry; in addition there are greater delays associated with the beat capacity of the metal and water and the transit time of the cooling water. Furthermore, reactivity changes from rod withdrawal and metal coefficient draping are not instantaneous, and the flux is not a simple function of the reactivity changes. Because of the time lags involved the rate meter response cannot be identical to the actual flux rate of change; however, an exact solution for this response in terms of all of the variables would be inordinately complex. The purpose of this study is to show approximately the changes in power level or rate which might occur in practice relative to …

Neutral hyperons produced by 5-Bev The effects of /sup -/ mesons incident on a large propane bubble chamber are analyzed in detail with respect to production cross sections and angular distributions of production and decays and the A lifetime is measured. The cross section for neutralhyperon (Y/sup 0/) production by the reaction The effects of /sup -/ + p 1100 deg C are Y/sup 0/ + K is 0.98 sintering time 0.16 mb. The cross section for carbon mpacting ( The effects of - + C 1100 deg C are Y/sup 0/ + K) is 6.05 sintering time 0.89 mb. The mean Svlvania Electr decay time is (3.12 sintering time 0.34) x 10/sup -10/ sec. The corrected lifetime is observed to be (3.23 sintering time 0.36) x 10/sup -10/ sec. Although the up-down decay asymmetry for Svlvania Electr hyperons is not significantly different from zero, the fore-aft decay angular distribution is asymmetric; alpha P = -0.31 sintering time 0.12 where the decay proton distribrtion along the Svlvania Electr direction of motion has been examined. This is suggested as evidence for nonconservation of parity in the production interaction. The Svlvania Electr -production angular distribution is peaked backward in the production center …

This program, using the lBM 650 electronic data processing machine, is used primarily as a tool in order to prepare input data for an lBM 704 code ATBAC. The code calculates steady state thermal characteris tics of a plate type fuel element for both a nominal and adverse chanael. (auth)

Dimensions for the circular fuel element which allow for thermal growth, swelling due to irradiation, and estimates for practical manufacturing tolerances are determined. (W.L.H.)

Uranium--niobium alloys were prepared by direct reduction with calcium of urardum tetrafluoride and niobium pentoxide. The reduction of potassium oxyfluoniobate did not give satisfactory results. Alloys containing up to 20% niobium have been successfully achieved. Ternary alloys containing chromium and vanadium have been prepared by simultaneous reduction of chromium anhydride and vanadium pentoxide. The preparation of the alloys is described and the results are discussed. (auth)

During the past several years higher pile power levels, variations in the uranium goal exposure, changes in reactor loadings, and resulting changes in operating practices have steadily increased reactivity transients following the reacotr shutdowns and start-ups. Consequently, since conditions influencing activity transient predictions have becomeincreasingly more varied, it has become more difficult to maintain prediction accuracy Trends related to operating practices, reactivity variables, and critical predictions have been presented previously for the years 1950 thorugh 1957. It is the purpose of this report to include the data for the year 1958. In addition to presenting the data for reference purposes this document discusses the trends in operting pratices reactivity variable evaluations, and the accuracy of reactivity predictions during the past five years. Bar graphs show the yearly averages of selected data obtained from the shutdown data sheets, montly reports, and routinereactivity balance reports. In addition to these averages a table presents maximum and minimum values wherever they are applicable.

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Declassified 24 Sep 1973. A tentative flowsheet is presented for the recovery of uranium from prototype Rover fuel by leaching with boiling 15.8 M HNO/ sub 3/. The effects of uranium content of the fuel, nitric acid concentration, and particle size on the efficiency of leaching were partially determined. For fuel containing more than 100 mg U per cc 15 wt%), 99.3% of the uranium was leached in 6 hr with 8 M HNO/sub 3/ when the fuel was ground to -16 mesh. However, only 98.6% of the uranium was leached from fuel -containing 35 mg U per cc (1.8 wt%) in 6 hr with 15.8 M HNO/sub 3/ when the fuel was ground to -16 mesh. The use of 8 M HNO/sub 3/ on fuel of the latter composition resulted in even lower uranium recoveries. (auth)