None

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.

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 …

None

None

None

None

None

None

None

None

None

None

None