From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."

Measurements of k∞, f, p, and ∈ have been performed in the PCTR in support of the EGCR Program. The values listed below were obtained for the 21.875-inch cell used in the PCTR measurements. They are for a nonabsorbing (helium or vacuum) atmosphere.

A coolant line rupture during operation of a high temperature gas cooled graphite moderated reactor would present a serious hazard. The reactor would immediately depressurize and a great deal of air would be introduced into the coolant stream. As the air passed over the graphite moderator a runaway oxidation reaction would probably ensue unless an adequate safety system were available. This investigation was designed to evaluate chlorine as a reactor safeguard to be used to control a runaway reaction. Throughout this study, a small amount of chlorine in an air stream has demonstrated the ability to substantially reduce the oxidation rate of graphite. This has been the case even where the principal oxidizing agent was molecular oxygen or ozone.

A report intended to correlate the RA and RC Column uranium equilibrium data presented in the reports cited in the introduction.

This report summarizes the research and development work carried out during June, July, and August, 1959, for Budget Activity 2790- Separations Development for Non-Production Reactors. The effort on Activity 2790 - Separations Development for Non-Production Reactors. The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

This report summarizes experimental results obtained for the General Electric Company under terms of Design, Development and Research Contrast DDR-33. A discussion of the results, the manner in which they were obtained and their probable accuracy are included. Suggested improvements or modifications of properties of this nature be contemplated.

An electromagnetic instrument similar to the Multitest was built and used to test 2200 uranium slugs. It was found that the equipment could be used to detect inclusions and cracks in the uranium, but that small cracks are not readily detectable on a production basis unless the material is absolutely uniform in inclusion content. The instrument can be used, however, to sort out hidden defects of a reasonable size and to reject grossly dirty uranium.

Four D-12 coil nests have failed since the start-up of the Redox Separations plant. Due to the high contamination and radiation levels of these vessels, the cost of decontamination has prevented the examination of all but one of the four. It was hoped that the examination of D-12 pot #2 would lead to an explanation of all four failures. This report will deal primarily with the metallurgical examination of the failure of D-12 pot #2.

The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.

Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).

Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.

From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.

Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.

Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.

Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.

Report that summarizes out-of-reactor tests undertaken to determine operating conditions, estimate damage from and extent of fretting corrosion, and describe continuing tests planned to monitor and eliminate this corrosion.

Fused uranium dioxide has desirable characteristics for fabricating high density nuclear fuel elements by swaging. Methods of preparing dense uranium dioxide particles being investigated at HAPO include are arc fusion, and sintering and crushing of low density powder. This paper reports the results of exploratory experiments to prepare fused uranium dioxide by induction heating of low density powder in graphite crucibles.

A study of the nuclear safety in the storage and transportation of PRTR fuel elements has been made. This study was based on 7-rod clusters of plutonium-aluminum allow fuel elements containing 1.8 per cent Pu by weight. Each cluster is 7 feet 4 inches in length and contains 270 grams plutonium. Drawings of the "New Fuel Storage Pit" (H-3-11030) have been reviewed for nuclear safety. Nuclear safety criteria for the design of a lead shielded fuel transfer cask as well as criteria for the storage of these fuel elements outside the facilities mentioned in the above drawings have also been reviewed. For water moderated systems, a homogeneous model of plutonium, aluminum, and water was used t evaluate the critical parameters. These results should be conservative. At the conclusion of an experimental program to determine criticality parameters of PU-Al alloys in light water, a theoretical approach will be developed to calculate such criticality parameters.