This report documents possible future outcomes of elections for the federal office.

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, Crawford Martin, regarding a legal question submitted for clarification: Under Article 1970-110a 1, Vernon's Civil Statutes (Acts 60th Legislature, R. S., 1967, Ch. 712, p. 1835), whether the Congressional Certificate" now in use by the Harris County Probate Court No. 1 is valid since the instrument to which it is sometimes attached is signed in one capacity and the certificate is signed in another capacity.

Interchannel flow through fuel element junctions can occur in production reactor fuel columns as a result of different pressure loss patterns in the two coolant subchannels. This interchannel flow is most significant during boiling conditions because, generally, the boiling length in each subchannel is different. These different boiling lengths result in divergent pressure loss characteristics in the subchannels and cause differential pressures to exist across the fuel element junctions. These differential pressures are the predominant driving forces for interchannel flow. The extent to which interchannel flow exists, and its effect on the thermal hydraulic characteristics of reactor flow channels has long been a question of concern in the design of electrically heated models of reactor fuel columns for laboratory experiments. Interchannel flow is quite unpredictable and subject to considerable variation due to mechanical and alignment changes at the junction. It is also very important because it significantly affects the total thermal-hydraulic performance of the fuel column. The purpose of this investigation was to analytically evaluate the effects of interchannel flow on the predicted thermal-hydraulic performance of a production reactor fuel channel and to develop accurate methods by which it could be simulated in electrically heated laboratory models.

With the exception of N Reactor, the production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once-through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quantity of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the coolant treatment process. Prior to 1961 the water treatment process had been improved to the point that reactor quality coolant could be produced using an average alum flocculent feed rate of 6 ppm. Laboratory experiments carried out in 1959 and 1960 demonstrated that a markedly increased removal of parent isotopes resulted when alum feed rates in the neighborhood of 20 ppm were used. Flocculant feed rate control based on producing a constant value of the electrokinetic charge (zeta potential) of the floc has been practiced at some water treatment plants. Although the hypothesis has not had universal acceptance in the water treatment field, laboratory and field data accumulated at Hanford indicated that further evaluation of the approach was warranted. In order to determine the effects of coagulant control based on zeta potential a half-reactor test …