Quarterly progress report on a project to test the radiation effects on metallurgy.

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."

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The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated values. The research and development program is estimated to require $3.6 million over a three-year period. Technical aspects of using oxide are discussed in general for N, K, and the smaller reactors. The variations in uranium-to-graphite weight ratio and operating conditions vary the limitations encountered with each reactor type with an oxide fuel cycle. Plutonium separation and uranium oxide recycle on site have been examined, and a technical review of the limitations and the additional process requirements are presented.

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 will be required to collect the difference in tax of 3 cents per package on cigarettes stamped at the old rate on hand as of the closing of business on June 30, 1965, 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: Whether the Banking Commissioner may approve an amendment to the bylaws of a State credit union authorizing the following purpose: “The purpose of this Credit Union is to promote thrift among its members, by affording them an opportunity for accumulating their savings; and by means of loans to members, and serving as a depository for other credit unions with a purpose of orderly interchange of funds between credit unions, to create a source of credit for provident or productive purposes or urgent needs.

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: Clarification of the holding of Attorney General Opinion C-472 (1965).

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: Reconsideration of Attorney General’s Opinion WW-201, relating to the question of whether a Railroad Commission employee may also serve as a joint board member for the State of Texas under appointment by the Interstate Commerce Commission.

Several theories have been advanced regarding the structure and characteristics of the aluminum hydroxide molecule when produced from alum in the water treatment process. The Water Treatment Task Force initiated this test to exploit a theory that increased adsorption of soil-leached elements, present in Columbia River water, by the floc particle would occur when the precipitate vas formed in its terminal pH state. This report discusses a half-plant test which was initiated at E Reactor Plant wherein the total sulfuric acid for pH correction was added with the alum to evaluate its affect on reactor effluent radionuclides.

This monthly report details reactor and materials technology activities during the month of June 1965.

This report covers the activities with regard to on-site customer irradiations as of May 14, 1965. The report covers the status of material undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes.

This is the fifth in a series of reports presenting the status and deterioration rates of the B. D, DR, F, and H biological shields. The last previous reports covering the period 1959 through March 31, 1961, indicated no significant decreasing trends in the attenuating effectiveness of the biological (iron-masonite) shields. At that time the combination of increasing average helium percentages and adding fringe poison in the smaller reactors resulted in corresponding reductions in shield temperatures below previous levels. Since then, there has been both an increase in reactor power levels and a greater emphasis on reduction of helium usage. Consequently, to limit biological shield temperatures and reduce the shield leakage, additional fringe poison has been employed for shield protection. This report covers the period from late 1960 through January 1, 1964.

Metallic fuel development is reported concerning N-reactor fuel element failures, target element development, target element closure welds, alternate target element closure systems, alternate uranium compositions, N-fuel support development, hot die size fuel cladding, improved closures for ThO{sub 2} elements, and N-reactor meltdown tests in the IRP. Corrosion and water quality studies are proceeding with emphasis on downstream pitting of aluminium process tubes, hydride formation in zircaloy tubes, groove and ledge corrosion of aluminium, pitting corrosion of carbon steel in filtered water, storage basin studies, examination of K reactor process tubes, zircaloy tube hydriding studies,nickel plated aluminium, effect of beryllium and uranium on the corrosion of zircaloy-2, and examination of zircaloy-2 graphite cooling tube. Thermal hydraulics studies include boiling burnout experiments for N-reactor and heat transfer experiments for K-reactor. Graphite studies include burnout monitoring in the N-reactor and graphite contraction.

This report covers progress in the following areas: production reactor support; plutonium recycle program; PRTR HPD core; corrosion and water quality; PRTR pressure tubes; reactor components development; plutonium ceramics research; ceramics (uranium) fuel research; swelling studies; irradiation damage to reactor materials; ATR gas loop studies; graphite studies; metallic fuel development; plutonium and U-233 fueling of a fast compact reactor; FFTF studies; radiation effects on metals; customer work (support of HTLTR and EBWR); physics and instruments; chemistry; biology; radiation protection; and technical and other services.

This monthly document details activities of the Battelle-Northwest Physics and Instruments Department during the month of July 1965. (FI)

This monthly report details Battelle Pacific Northwest Laboratories activities for the month of May 1965.

This report discusses research at the Hanford production reactors on reactor materials and reactor technology.

This report details activities of the Reactor and Materials Technology Department for the month of February 1965.

A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward optimizing deposition process parameters to attain control of qualities such as coating thickness, uniformity, density, impurity content, and surface quality. Substrate penetration methods have been investigated in the interest of completely eliminating the interface between the fueled substrate and cladding. In addition, the effects of process parameters and post-cladding heat treatments on the fuel retention properties of clad composites at 4500 degrees F (2480 degrees C) in hydrogen for 2 hours have been evaluated. As a result of work performed during the first phase of the program it has been shown that the rate of deposition of tungsten from WF 6 and the uniformity of the deposit can be varied in a predictable and reproducible manner by exercising control …

From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.

Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.

From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element.

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