Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.

Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.

This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.

Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In addition, the development of strontium-90 as a major product requires increased flexibility in the utilization of these casks.

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

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

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather than the product streams.

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.

A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar to processes used by the Isotopes Division at the AEC's Oak Ridge operation served to separate the desired fission products from one another and from the corrosion products (1,2,3).These separation schemes employed careful step-wise pH adjustment to precipitate first the iron and then to separate the desired fission products from one another. The flowsheets were demonstrated on a pilot-plant scale with full-level plant waste. However, since the earlier work was complete, plant operations have been modified....

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.