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The adiabatic single crystalline elastic constants of six Mg(Cu, Zn)/sub 2/ cubic Laves phases have been determined by the ultrasonic pulse-echo technique over the compositional range 10 to 50 mol % MgZn/sub 2/ and over the temperature range 4.2 to 300/sup 0/K. In addition the elastic constants of the hexagonal MgZn/sub 2/ Laves phase were measured as a function of temperature. A minimum exists in the compositional dependence of the cubic Mg(Cu, Zn)/sub 2/ phase at 20 mol % MgZn/sub 2/ for all three directly measured values and the anisotropy ratio shows a maximum at the same composition. These phenomena may be related to the fact that their Fermi surface touches the (311) faces of the Brillouin zones at this composition. The various energy contributions to the elastic shear constants were considered and it was concluded that the Fermi energy has to be included to achieve satisfactory agreement between the calculated and measured elastic constants. The Debye temperatures were calculated and were found to decrease at low zinc contents and then increase at compositions above 20 mol % MgZn/sub 2/ for the cubic Mg(Cu, Zn)/sub 2/ phase. The initial decrease is probably due to the substitution of the heavier zinc …

Spot-radiographs, per Combustion Engineering instructions, on the head-to-shell weld, No. 160-4, on steam generator No. 4B have been completed. No weld discontinuities in excess of specification limitations were detected. Radiography on the 10-foot diameter head-to-shell weld, No. 160-4, on steam generator No. 4B, cell 4, 109-N Building, 100-N Area has been completed after stress relief. The weld complied with the requirements of the ASME Boiler and Pressure Vessel Code, Section III (Nuclear Vessels), 1968 Edition. Whole-body counts were obtained on 506 children of the Fruitland School in Kennewick. These measurements will be related to foods the students ate as indicated by diet records. It now appears that the relative merits of monitoring river temperatures at 100-F vs. Richland in relation to State standards will be more dependent upon the extent to which power levels may have to be reduced than upon the number of days out of the year when such reductions are necessary.

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The Washington State Pollution Control Commission water quality standards for interstate and coastal waters were adopted in December of 1967. The temperature standard was identified as the most restrictive of these for the Hanford operations. This report compares the temperatures and thermal additions to the river from Hanford during 1967 with the limit specified by the Washington State Pollution Commission. Two factors complicate the problem of evaluating Hanford operations that alter the temperatures in the river: (1) natural heating or cooling imposes temperature changes between the plant and downstream measuring locations, (2) wide flow fluctions on a daily and weekly basis resulting from upstream dam regulation are reflected in similar temperature fluctuations. Using 1967 data this report identifies the Hanford temperature contribution at both 100-F and Richland. The effects of daily and weekly averaging as -well as measurement location are presented.

This report contains raw data of temperature measurements of the Columbia River and its tributaries.

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The concentration of inert elements and radioisotopes contained by the films on both fuel elements and aluminum process tubes were measured in selected samples taken from specimens of varying in- reactor exposures. The amounts of radioisotopes contained on a unit surface at any particular location on the three tubes increased with longer exposures, however, the differences were less noticeable in the case of isotopes of shorter half-life. Inert element concentrations were quite constant at a given location in the three process tubes, and the linear distributions could be described as an exponential function of distance. The linear distribution of inert elements on a fuel column with sixty days exposure could also be described by this function although higher concentrations were present. A different deposition pattern was exhibited by two fuel columns of lower exposure. Film composition was uniform along the length of the various process channels, with relative values approximating the respective ratios of the parent isotopes in process water. Corrosion of aluminum process tubes was shown to contribute only minor amounts to the radionuclides contained by the films on the tube surfaces. It is therefore concluded that most of the materials comprising the in-reactor film originated as impurities in …

Start of the development of new processes to extract mint can be a gradual program. The most promising of early results lies in the area of Isotopic Purification. Steps have been initiated to start development work on separation and purification of mint gas by chromatography. This method has the added advantage over columns as three gases, hydrogen, deuterium and mint may be separated in one operation. Should it appear that this method may fail, a second approach would be development of a packed column. Even with a change of the basic extraction process, isotopic purification is required and the improvement of such facilities would serve to provide the product at a reduced initial capital cost as well as reduced extraction cost. Work can proceed at the same time with development of a dissolution process. As noted in Appendix I, a unit extraction savings in the order of 20 percent can be expected since, in the most simple form, expensive furnace pots would be replaced by inexpensive crucibles.

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Mass formulae for M = 0 and M = 1 Toller families are derived using the standard tools of the S-matrix theory.

It is the purpose of this report to present data obtained from the routine reactor effluent radioactivity monitoring program as well as the results obtained from the research and development program directed toward the reduction of effluent radioactivity.

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The following is all the information the authors can get on the graphite bar history from the A and G test holes at C-Reactor. The A test hole was charged with 18--23 1/2 inch long graphite bars before the original startup of C-Reactor. This was 6/12/53. On 9/21/63 seven of the graphite bars were discharged. Position {number_sign}18 thru {number_sign}12. Positions {number_sign}11 thru {number_sign}1 are still in the reactor. Data on the seven bars discharged and the eleven bars still in the reactor is given. On 7/21/59 a 2-foot section of tube block was removed from the G test hole. This tube block had received 15,462 MWD/AT at time of discharge. On 4/21/60 three solid graphite bars were removed from the G test hole. These bars received a total of 18,642 MWD/AT. There are six more bars in the G test hole. They are in positions 1 thru 6. The approximate total exposure is given.

This monthly report details Douglas United Nuclear, Inc. activities during the month of October 1968.