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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, Waggoner Carr, regarding a legal question submitted for clarification: Riparian Water Rights of the Department of Corrections on Oyster Creek, Fort Bend County, Texas.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether funds currently appropriated to the Texas Animal Health Commission may be used to determine which employees are susceptible to blood poisoning from being exposed to toxic insecticides used in the Screwworm Eradication Program.

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, Waggoner Carr, regarding a legal question submitted for clarification: In a mental health case, can the trial judge properly direct the patient and his family not to pay the $5.00 statutory judge’s fee listed on the cost bill for such case and related question.

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, Waggoner Carr, regarding a legal question submitted for clarification: Hospital care of indigent patients in Ochiltree County.

The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditions common also to the side and bottom thermal shields. Concern for possible deteriorating condition of the top cooling tubes has increased with the discovery of a leaking cooling tube at the C Reactor. This report provides information of the present condition of the cooling tubes and discusses continued surveillance of their condition which is required for evaluation of their continued serviceability.

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This report summarizes the considerations and analysis leading to the design of the SNAP-15A generator, a Pu-238 fueled, metal thermocouple generator providing about 1 milliwatt of output power at greater than 4, 5 volts of years with very reliability even under extreme environmental conditions.

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Preliminary results of the irradiation of control drum bearings in a static test, conducted at the Plum Brook Reactor Facility in Sandusky, Ohio, on October 14-15, 1963, are described in this report.

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This report addresses the Bendix TPCV actuator presentation.

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A hybrid approach was adopted in the use of an on-line computer in setting up and analyzing nuclear physics experiments. In addition to the usually cited advantage of online flexibility and the ability to do off-line calculations, the general purpose computer can simulate data by preserting the results of off-line calculations to the experimenter in a format identical to that used for data display. As compared with off-line calculations at a computer center with subsequent hand or machine plotting, the use of the build-in display hardware provides a more convenient comparison of theory with experiment, as well as greater ease and speed. The advantages of on-line data transformation are preserved without accompanying limitations on the rate of data taking. The data from the experiment consisted of energy correlations in two-particle coincidence experiments. The loci of points in energy-energy space fulfilling energy and momentum conservation were calculated, displayed, and photographed before each experimental run. Interpretation of the experimertal data was assisted by modulation of the loci (of the number of counts per channel) according to the predictions of various models. (auth)

The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)

LRL has the responsibility of demonstrating the feasibility of a reactor for use as a power plant for a low-altitude, high-Mach-number missile. This reactor is literally a very high power air heater which must work at temperatures in excess of 2000' F. The reactor is exposed to high loads so one of the primary problems is providing high temperature structure. Considerable effort has been devoted to developing ceramic structural elements. One of the materials considered for this purpose is silicon nitride. In ceramic structural elements operating over large temperature ranges, a major problem is coping with thermal stress. In this respect there is a similarity with the radome problem. The work on silicon nitride at LRL consisted of limited fabrication studies (principally for familiarization), measurement of properties of interest to the application, and funding of fabrication scale-up efforts.