From introduction: "This report describes research on the development of compositions and techniques for porcelain enameling uranium fuel slugs used in Hanford production reactors."

Thesis presenting data taken on experimental nuclear magnetic moments for beta spectra of the mirror nuclei with A-19 to 39.

Abstract. A satisfactory method has been found for dissolving thorium metal and thorium oxide in heat-treated 25-12 stainless steel vessels without excessive corrosion of the vessels. The dissolution medium consists of strong HNO3 containing a small amount of fluoride or fluo-silicate. the fluoride required has no harmful effects on a subsequent solvent-extraction step for a separation of uranium isotopes from the dissolved thorium.

This partially annotated bibliography contains references on advanced space propulsion units. References are also included on auxiliary power units, energy requirements, and mission requirements. The references are arranged alphabetically by title, with corporate author and subject indexes provided. This bibliography is issued in two parts: CNLM-2370-3, Part I, contains unclassified references; CNLM2370-3, Part II, contains classified material. Sources used in compiling this bibliography are: Abstracts of Classified Reports 1957-June 1960, Applied Science and Technology Index 1958-June 1960, ASTIA 1958-June 1960, Engineering Index 1957-1959, Industrial Arts Index 1957, Nuclear Science Abstracts 1957-June 1960, U.S. Government Publications Monthly Catalog 1958-June 1960.

This report analyzes experiments on the production of zirconium tetrafluoride and discusses the reactivity data taken after various methods.

Am III and Pu III have been recovered on a plant scale by extraction with tributyl phosphate from slag and crucible and other recovery solutions. Process losses were 0.03% Am and 0.01% Pu. The product stream contained 0.08 gram Am per liter and 0.15 gram Pu per liter. The final solution cleanup to allow discard (total alpha activity equivalent to less than 10(-4) gram Pu per liter) was accomplished by tributyl phosphate extraction of Pu III under conditions of low acidity and high nitrate.

The F-48 columbium base alloy maintains useful mechanical properties for structural application up to 2600 degree F. Short-time tensile and creep rupture strengths have been determined for four F-48 plates, each from a different heat and with a different work history. Flow testing in a high-temperature, high-pressure air stream has been conducted to study oxidation behavior of the bare meatal. Auto-ignition is found to occur at a stream temperature of 2600 degree F. The phenomenon appears to be temperature dependent only. Development of an oxidation protection coating, utilizing environmental flow test apparatus, is proceeding.

This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.