" A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to which the encapsulated gases and particles can diffuse and be removed."

Technical report. From Introduction : "The nuclear volume dependent isotope shift of optical spectral lines has long been a very useful means for studying the changes in the nuclear size or shape for different isotopes of heavy elements."

Irradiation of thorium for the production of ``clean`` U-233 at HAPO began in CY 1963. Several small-scale tests, involving from gram size quantities up to a few elements, were successfully conducted and the results from these tests, coupled with theoretical predictions, indicated the desirability of further investigation. This test is one of the final steps in the pilot irradiations of ton quantities of thorium oxide target elements. The objectives of this test are to (1) authorize the irradiation of about two tons of thorium target elements in central zone process tubes of KE Reactor, (2) determine the reactivity effects of an enriched uranium-thorium oxide (E-Q) loading in the K Reactors, (3) demonstrate the feasibility of using the K Reactors in production of ``clean`` U-233 and (4) provide sufficient irradiated thoria material to permit demonstration of the chemical processing capabilities.

This document provides the specifications for the uranium billets to be used for fabrication of the driver fuel elements for a coproducer demonstration in N-Reactor. The specifications for uranium billets for the standard tube and tube geometry are listed in HW-67575 Rev3, ``Specifications for Uranium Metal Billets for NPR Fuel Elements,`` July, 1963, and in HW-76155 REV3, ``Chemical Specifications for Uranium Billets for NPR Fuel Elements,`` dated June 12, 1964. This document specifies the exceptions applicable to the fabrication of the billets for the coproduct demonstration program. All requirements of the reference specifications listed above not specifically excepted by this document shall apply, The numbers in th subheadings listed below correspond to the numbers in HW-67575.

The decontamination cycle (HA) at Purex has occasionally responded favorably to additions of waste rework material. The effect, exhibited in increased extraction of plutonium and improved decontamination from fission products has become known as the ``Tonic effect.`` Efforts to find the agent or agents in waste rework which are responsible for this effect have not been successful. Workers at ORNL, principally C. A. Blake, found that various materials decreased the distribution ratios of zirconium-niobium ruthenium activity. This work covered oximes, ketones, and oxalic acid in the Purex HA system. Their work ended with the conclusion that oxalic acid was the most effective of all agents tested. This paper describes the work by Separations Chemistry Laboratory designed to test these and other additives in the HA system at Purex.

The feasibility of fabricating aluminum clad, low-density ({approximately} 65 per cent theoretical density) thoria elements using thoria produced-by a modified Sol Gel process, low frequency-low energy vibration for compaction, and the TIG welding process for closure welding has been demonstrated by Hanford Laboratories (HL). They have also assembled thoria fuel elements for the initial irradiation to produce 1 to 2 kgs. of U-233. At this time, it is expected that Hanford will be asked to produce about 25 kg. of ``clean`` U-233 and that authorization to proceed with this program could be expected sometime between now and late fall of CY 1964. The requirements in terms of equipment and manpower, and the time schedules to produce this quantity of U-233 have been published and it was indicated, based on best estimates made at the time, that finished thoria fuel elements could be produced 7 months after authorization of the program, and the full 60 tons of fuel elements completed 9 months after authorization. Approximately $125,000--150.000 of capital equipment in Production Fuels were estimated as being required to produce the quantity of fuel elements required, including prototypes used in engineering development. This report reassesses the Production Fuels Section capability to meet …

Production Test IP-584-D, Supplement B authorized the irradiation of target assemblies in KER-1 and KER-2. Furthermore, the production test authorized that these target assemblies be irradiated with)other approved production tests; for this test, N Reactor inner fuel elements (NIE-1) will be irradiated. The production test required that specific operating conditions and loading patterns would be approved by the managers of Testing, Process and Reactor Development, and Process Technology Subsections prior to charging.

Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to use tubular dummies for this portion of the support charge which are less expensive to fabricate and which are easily identified during the charging-discharging process. However, there exists a remote possibility that one or more tubular pieces could be inadvertently placed in a rear nozzle resulting in a flow restriction in the process tube. These arrangements of tubular support pieces in the dummy pattern, i.e., tubulars positioned against the fuel column and/or in the process tube rear nozzles, have been hydraulically tested to determine if there is adequate and unrestricted flow at normal operating header pressures.

The N-Reactor Department Research and Development Program for FY 1965, 1966, and later years is structured to achieve the following general goals. (1) Assurance of a high level of nuclear safety; (2) Assurance of achieving full plant life; (3) Reduction in operating costs for a given production rate; (4) Increase in production rate without proportionate increase in operating costs; (5) Savings in capital outlays necessary to achieve stated reductions in operating cost or increases in production; (6) Production of new products of value; (7) Savings in capital outlays or operating costs to achieve a given level of plant safety. The program is divided into three general categories; Reactor, Metallurgy, and Co-Product. The Reactor category is further divided into physics studies, thermal hydraulics studies, zircaloy process tube development, control, instrument and system analyses, chemistry, engineering research and development, gas, atmosphere studies, graphite studies, and nuclear safety research.

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To provide the NERVA test program with a temperature measurement system of sufficient accuracy to satify present and future requirements, a cryogenic temperature measuring system was designed and developed employing a platinum resistance thermometer (RTT) as the sensor.

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The Blake Rhometer operating range was extended from 600 to 1000 deg F and a variable-orifice plugging meter was developed. Both instruments were evaluated in the Atomic Power Development Associates Scdium Technology Loop against weighed or metered contaminants. The loop injection series included: water, hydrogen, carbon monoxide, carbon dioxide, and methane gases; and tea bag injections of sodium carbonate, sodium hydride, sodium hydroxide, and sodium monoxide. Cover gas was monitored and temperature varied during and after each injection run, and the test loop cleaned by cold trapping after each run. A Continuous Hydrogen Monitor attached to the loop cover gas system and a Nickel Diffusion-Tube Hydrogen Monitor connected to the loop proper were evaluated for sensitivity and response. (auth)

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The computer program FATT for calculating the transient temperature distribution in the EGCR core is described. The program, in FORTRAN for the IBM 7090, provides an arbitrary choice of axial increments for the reactor core. The heat transfer coefficients are made temperature-dependent. Provisions are available for plotiing the results from the program on the Calcomp plotter. The equations and some typical results are included, and the finlte difference method of solution is described. (auth)

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 a county is authorized under Art. 6830, Vernon's Civil Statutes, to levy a tax for maintenance of seawalls, in addition to the tax levy for service on bonds issued for the purpose of building such seawalls so long as the levy for both purposes stays within the 50 cent limit.

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; Questions relating to the State Board of Education's authorization for the creation of a county junior college district, and the commissioners court's authority to order elections thereunder.

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 Comptroller of Public Accounts in Authorized to release the State’s Total Occupancy tax lien when the amount of the tax liability claimed by the State has been paid under the protest statutes?

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: Travel expense allowance under Article 2350o, V.C.S.

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 paragraph 9 of Chapter 7 of House Bill No.11, Acts of the 56th Legislature, Third Called Session (Article 7.08 Tax. Gen.), is in conflict with the Texas Constitution.