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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: Validity of appropriation to the Upper Red River Flood Control and Irrigation District.

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: Construction of House Bill 1170, Acts 59th Legislature, 1965, Regular Session, Ch. 400, p. 828, which amended Section 4 of Article 1042b, Vernon’s Penal Code, pertaining to the sale of flour in quantities under two pounds and related questions.

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The Purex Plant was originally designed for the chemical processing of irradiated natural uranium. It has been used nearly exclusively for this purpose during its approximately ten-year operating lifetime. However, during the winter of 1964--1965, a special processing campaign was planned and accomplished in which approximately 6 tons of irradiated thoria targets were introduced to the plant, and the thorium-232 and uranium-233 were successfully separated and purified on a demonstration basis. For the demonstration thorium processing operation (6-ton test) of the winter of 1964--1965, process specifications were issued. These specifications were necessarily specific to the particular campaign inasmuch as a rather unusual processing scheme was required, by virtue of the small tonnage involved and the equipment limitations of the plant. Thus, for the relatively large operation subsequently planned, other process specifications are required. The purpose of this present document is to provide these specifications. Depending on the manner and extent of thorium -- uranium-233 production developments, these present specifications may have future application, at least in part. In addition to the process specifications, this document includes a section describing the flowsheet, and a section in which the technological bases for good process control are presented. In conjunction with the specifications, …

The power of high flux fuel assemblies and three-tube drivers planned for future operations is limited by the burnout safety factor (BOSF). In the past, the power of standard production fuel assemblies was limited almost always by one of the hydraulic limits, and in most cases the assemblies operated at powers significantly below that permitted by the BOSF limit. The burnout conditions for an ``ideal`` fuel surface have been well established in mockups at SRL and Columbia University. Little experimental data are available on nonidealities (such as local hot spots), although calculated factors are applied to the BOSF to account for certain nonidealities. Because of operation at the BOSF limit, better knowledge is needed of the effects of nonidealities and other factors on heat transfer burnout of fuel surfaces. This memorandum presents a program designed to give a better understanding of BOSF.

This memorandum provides the minutes of the 7th meeting of the Livermore Vulnerability Committee. The Laboratory commitments in the Tapestry experiment, with particular reference to those experiments proposed in the Polaris MK 2 and the Minuteman MK 2 programs.

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Report on an evaluation of the Sand Springs Range as a possible location for an underground nuclear study (Shoal Event). Various tests to determine the site's suitability included aerial photography and mapping of the area through various means; drilling and bulldozing to conduct mineralogical and other physical evaluations; gravity, aeromagnetic, and refraction surveys; and studies related to the hydrology of the location and surrounding areas.

This report details post-irradiation annealing studies at 610 and 630 C which have shown that a submicron dispersion of UC in uranium is effective in reducing mobility of fission gases in uranium irradiated to 1.4 {times} 10{sup 20} fissions/cc (0.3 percent burnup). Electron microscopy of both the as-irradiated and the annealed samples show that a large population of less than 0.1{mu} UC particles develops which is believed to be responsible for the decreased swelling during annealing. Uranium fuel elements containing 390 ppm Fe and 840 ppm aluminum shows substantially less swelling both during irradiation and during post-irradiation annealing than uranium containing 140 ppm Fe and 120 ppm Si. Zircaloy-2 clad thorium-uranium fuel continues to show excellent performance in a pressurized water loop. Fuel swelling is currently 1.0 percent at an exposure of 3.7 {times} 10{sup 20} fissions/cc (11,000 MWD/T).

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Plates documenting results of some tests performed during the site evaluation of the Sand Springs Range including aerial photography, various types of mapping and surveying of the physical and hydrological aspects of the location, and other supplementary materials.

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The purpose of this report is to present a preliminary analysis of pressures in the K-Reactor downcomer approach section during bulk outlet water temperature transients.

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There are four district stratigraphic units within the Pasco Basin which if interpreted on the basis of recent field evidence and described properly could be traced over most of southeastern Washington. At the present time these post-basalt sediments are described in the literature in such a way as to make extensive correlations impossible. Some descriptions overlap more than one unit whereas others describe only a part of the unit. It is proposed that all interested geologists in the Pacific Northwest now consider reconciling the differences which exist in the names and descriptions of those sedimentary deposits in light of this new evidence.

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This report addresses the calculational models for beta dose from spherical particles.

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