This report provides the N-Reactor research and development budget for fiscal year 1967 and modifications of the budget for fiscal year 1966.

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: Constitutionality of House Bill 8, 59th Legislature, Regular Session.

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 the Seawall Commission for Matagorda County created by Chapter 4, page 11, 43rd Legislature, Fourth Called Session, 1934, is still an effective body, and alternative 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, Waggoner Carr, regarding a legal question submitted for clarification: Constitutionality of House Bill 503 relating to purchasing procedures of gas and electric companies of certain cities.

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: Constitutionality of Senate Bill 163, Acts 59th Legislature, 1965, the “Economic Opportunity Act of 1964.”

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; Taxation of Improvements on Land.

The use of metallic uranium fuel elements on a large scale in a pressurized water cooled graphite moderated power reactor environment in N-Reactor not only represents an extrapolation from previous Hanford fuel technology but it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites. The major benefit to be achieved through an extensive and continuing fuel program is attainment of the full capabilities of the N-Reactor at much reduced fuel cycle costs. The current N-Reactor fuel design represents the best engineering judgment of what is required for adequate performance. While the design is intentionally conservative, some features may not fully provide the level of performance required to sustain efficient reactor operation. Results of production-scale irradiation experience and special test irradiations will provide direction to a continuing program to correct any excesses or deficiencies in the initial fuel design. Reduction of unwarranted conservatism in the design will lower fuel fabrication costs, and correction of deficiencies will lower irradiation costs through increased time operated efficiency. Costs of …

The graphite movement which has occurred at the various reactors has been characterized by two problems: (1) Crooked channels and (2) cracks and miscellaneous voids where pieces of blocks are missing. Of these problems, the cracks and voids have been the most serious in the case of ball drops. Alleviation of the crooked channels can sometimes be accomplished by graphite removal methods such as broaching, but unless some method is found to prevent the balls from entering cracks, the total effect of a ball drop would still be intolerable. Of the two methods of closing the cracks, a paste caulking procedure is anticipated to be less expensive than sleeving, both in terms of cost of the operation and the number of process tube channels which might be lost. If the VSR channel does not require drastic straightening or entry of large tooling, satisfactory caulking can be done without removal of the step plug. ``Poison`` chain may be considered as an alternative to caulking or sleeving for those outer VSR channels where the sole use of balls is for ``total control`` rather than ``speed of control.`` The objectives of this test are (1) to authorize the experimental crack filling of one …

This report discusses the production of weapon grade plutonium and tritium as an economically attractive mode of operation for N-Reactor. With the successful completion of the proposed research and development program coproduct production in N-Reactor could begin in January 1967. Approximately 5 kg of tritium could be produced at a reduction in unit total cost of up to $7 per gram equivalent when compared to other modes of operation of N-Reactor that yield only-weapon grade plutonium. Achieving this production level and unit cost requires a fuel and target design that will subject the materials to more severe temperature and exposure conditions than for the tube-in-tube design. Analyses of existing knowledge and experimental results obtained to date are very encouraging. However, there is a continuing need for additional experimental verification of the limiting conditions for both fuel and target to permit the specification of a production fuel and target design. The incremental cost of this program is estimated to be $1,055 million in FY-1965, $0.796 million in FY-1966 and $0.450 million in FY-1967 for a total of $2.3 million. The principal benefits to be derived from this expenditure of research and development funds are lower unit grade plutonium. When the reactor …

The objective of Production Test IP-725 was to investigate the reaction rate between graphite and carbon dioxide in F Reactor at a temperature 50 C higher than that currently permitted by Process Standards. After approval of the test, the temperature limit was increased from 650 to 700 C. After approximately three weeks of operation with the-higher temperature limit, the reactor was shut down and the graphite oxidation monitor samples which had been inserted for this test were discharged and measured. It is believed that sufficient data have row been obtained from the first phase of the test to warrant investigation at an even higher temperatures. It is therefore the objective of the supplement described in this report to raise the graphite temperature limit at F Reactor by an additional 50 C to a limit of 750 C.

This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.

Declassified 28 Aug 1973. W--20 vol% U0/sub 2/ honeycomb structures were successfully made by two fabrication methods. One method involved stacking of individual unsintered hexagonal tubes, followed by isostatic pressing and sintering. The other method formed the unsintered honeycomb as a unit which was then sintered. The sintered structures, eonsisting of a close array of 1-1/2 in. long hexagonal channels, had densities ranging from 94 to >97% of theoretical. In addition to honeycomb fabrication, two methods are described for cladding the interior honeycomb surfaces to prevent U0/sub 2/ loss during high-temperature operation. (7 tables, 32 figures). (auth)

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This report discusses the anti-trust act that would be effective in eliminating certain forms of price discrimination which is believed were destructive to competition.

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