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, Will Wilson, regarding a legal question submitted for clarification: Authority of the Interim Committee on Migrant Labor to expend State funds for the employment of Legal Counsel, research staff or clerical help.

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, Will Wilson, regarding a legal question submitted for clarification: Whether the National Guard or the State of Texas is required to pay additional medical or hospital expenses to or on behalf of servicemen in the event of further treatment or rehospitalization under the facts stated, and related questions.

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, Will Wilson, regarding a legal question submitted for clarification: Exemption from ad valorem taxes of property belonging to The Cartmell Home for Aged and Orphans.

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; Effect of the order of the Commissioners' Court of Hardin County entered on March 24, 1969, on valuations on the county ad valorem tax rolls which had been finally approved by the Board of Equalization on January 22, 1969.

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; May beer be legally possessed by an employee of a beer retailer on the latter's licensed premises in a 2 5/8 gallon container bearing the beer brand name and which has been filled from a tax paid legal-sized 1/2 barrel of beer purchased by the beer retailer from a beer distributor.

The properties of radioisotope fuel compounds and fuel capsule materials which are pertinent to the design and operation of radioisotope heat sources are outlined. These properties are grouped into the following categories: intrinsic, extrinsic, and compatibility. The properties of strontium titanate as the fuel and Hastelloy C as the capsule material are evaluated. (D.L.C.)

A transistcrized, portable alpha-survey instrument was developed. Features included are: time-proved air proportional probe (18 in./sup 2/ area); D- cell powered, built-in speaker and audio amplifier; circuit board modules; and sufficient sensitivity and high-voltage power to operate almost any similar type of detector without modification. (auth)

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Plant scale tests were conducted to determine the feasibility of decomposing the nitrous oxide in dissolver off gases with a heated rhodium catalyst. The test results from two fixed bed reactors operating on off gases containing between 14.2 and 19.8 vol.% nitrous oxide show that the nitrous oxide content can be reduced to less than 0.05% with catalyst bed outlet at 1300 to 1500 deg F and space velocities at 472 to 700 hr/sup -//sup 1/. Rate constants appear to be comparable to those reported in the literature. Suggestions are made for the design of a permanent installation. (auth)

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This volume presents the charts and some backup material presented to members of the Division of Reactor Development on April 17, 1961.

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Research on numerical analysis, biological and medical statistics, and programming is reported. Programming and analysis work involved chemistry, health physics, analytical chemistry and chemical technology, neutron physics, physics, reactors, reactor chemistry, metallurgy, and computer operation and programming. Agricultural research and the training courses offered are also reported. A list of lectures, papers, and publications for the report period is included. (D.C.W.)

The problem of tube collapse by external pressure has been investigated experimentally. A graphical solution developed to simplify inelastic collapse design problems was shown to agree with the test results. The von Karman reduced modulus was used in the graphical solution to correct for the stress redistribution caused by yielding. The effects of the geometric imperfections of ovality and wall thickness variations on collapse pressure were shown to be related to the stress-strain behavior of the material. The concept of a critical time'' was discussed in regard to creep-buckling phenomenon. (auth)

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Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energy of the lattice because of interstitial and vacancy defects. Radiation changes such as stored energy and dimensional expansions can be removed by thermal annealing in which the graphite is removed from the radiation field and heated to a temperature above the irradiation temperature. The thermal annealing of irradiated graphites shows that the greater the irradiation dose, the greater is the recovery obtained at a given temperature. In periodically irradiated graphites, the 200 deg C stored energy no longer increases as it does in continuously irradiated graphites. Thermal annealing not only removes radiation damage but redistributes and creates it. (H.G.G.)

The elastic scattering of C/sup 12/ ions from Ar, Fe, Ni, Ag/sup 107/ In, and Ta was measured as a function of angle, at a laboratory-system energy of 124.5 Mev with the Berkeley heavy-ion linear accelerator. The experimental equipment and techniques are discussed. The angular distributions show the same general behavior as previous heavy-ion elastic scattering experiments. The experimental data were analyzed with the semiclassical Blair model as modified by McIntyre. Very good agreement with experiment was obtained. The measurements were taken with 1% statistics in order to study the structure of the angular distributions in greater detail, because only by fitting the details in the structure was it possible to obtdin unambiguous sets of parameters. The parameters indicated a nuclear radius of 1.45A/sup 1/3/ x 10/sup -13/ cm, and a nearly constant surface thick ness of 1.6 x 10/sup -13/ cm. Total reaction cross sections were obtained. A rainbow-model analysis by Goldman of the data is given. Existing alpha - and heavy-ion scattering data were analyzed with the McIntyre model and compared with previous optical-model analyses of the same data. It was found that, by independent analysis, the two models give the same imaginary phase shifts for all partial …

Thulium oxide can be irradiated to meet the desired specific heat generation of 1.5 watts per gram as part of a flux amplification test, which will be conducted the early part of FY-1965. To obtain the heat generation level, is calculated that a 120-day irradiation will be required at a flux of 1.1 {times} 10{sup 14} neutrons/cm{sup 2}-sec. if the proposed target element is modified by reducing the thulium oxide wafer thickness from 0.080 to 0.050 inch. Also, the length of the target element should be reduced to not more than 20 inches to minimize the possibility of sticking in the process tube. This would require four targets rather than a single element as proposed. Prior to undertaking this irradiation, it would be desirable to place a prototype target element in the Hanford Test Reactor to determine the approximate rise factor (change in neutron flux level between the target element and adjacent tubes of fuel elements) in order to more precise data for planning the loading pattern in the production test.

Because of rod-sticking problems at DR Reactor, a knuckle rod of B Reactor design was installed in vertical safety channel number 28. The substitute VSR, which has a smaller diameter than the original DR rod, has been tested for its operational feasibility including both drop time and reactivity effect. The reactivity effect of the rod was estimated by comparison of the reactivity transient caused by insertion of the specific B-type rod after scramming into the pile, with similar transients caused by normal vertical safety rod in an adjacent channel. This document lists the indicated relative control strength of the rod as an empirical basis for future safety calculations. Results indicate that the B-type knuckel rod in DR reactor is about 80% as strong as a normal DR vertical safety rod if used in equivalent flux distribution and location; this makes it reasonable to assume that the local control strength of the B-type knuckel rod is 98 {mu}b.

This document is divided into the following sections: Fuel element swelling model, tubular fuel element irradiations, Zircaloy-2 cladding strain study, comparison of swelling of U-2 wt % Zr and unalloyed uranium, and Th-U alloy fuel.

Two chemically nickel-plated, internally and externally cooled, Hanford production fuel elements, which were irradiated to approximately 800 MWD/T as part of PT-IP-263-A, were transferred to the Radiometallurgy Laboratory in December 1960. The elements were selected for detailed examination because one had incurred a hot spot during irradiation and the other contained some unusual cracks in the nickel plate. Prior to irradiation, both fuel elements had been baked at 300 C to heat-treat the nickel plate. Also, the nickel plate of several unirradiated elements was damaged by scraping, marring, scratching and punching. The elements were exposed for six weeks to 105 C basin water, which was approximately the length of time the irradiated elements were in 105 C basin prior to transfer. Two unirradiated elements were submitted for comparison with irradiated pieces. The examination was requested by Process Engineering, Fuels Preparation Department; and Process and Reactor Development, Irradiation Processing Department, to determine the effects of irradiation on elements with improved nickel plating and to aid in evaluating the nickel-plated fuel element program.