From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."

A compound decision problem is the simultaneous consideration of a large number of statistical decision of identical nature. The work of Hannan and Robins are extended to the derivation of optimal asymptotic procedures in the sense of regret risk convergence for a variety of compound decision problems. Convergence theorems are derived. (D.L.C.)

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Partial abstract: "This report is based: (1) on information developed in earlier high explosive experiments which determined the optimum spacing and burial depth of charges in a row to produce a channel uniformly wide and deep, and (2) on the Sedan and Danny Boy experiments, which provided data on dimensions of nuclear craters in both soil and basalt rock. This information has been combined with the 1947 route surveys of the Panama Canal company, and estimates have been made not only of the number and yield of nuclear explosives required to excavate a Transisthmian canal with nuclear explosives, but also of the cost of the explosives and the cost of their replacement."

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The extrusion forming of ceramic powders may be economically interesting in the field of nuclear fuel fabrication. When applied to the forming of rod-type uranium dioxide fuel, extrusion processes have been able to produce cylindrical bodies with length-to-diameter ratios much greater than those of the conventional die-pressed pellets. Furthermore, after being sintered, the extrusions have exhibited densities at least as high as those of sintered pellets. Thus, extrusion forming may offer reductions in handling during fabrication and, at the same time, provide a fuel with improved performance characteristics by decreasing the number of discontinuities in the fuel column. This report reviews the production of these extrusions, sets forth some of their characteristics, describes the materials and processes employed in cladding them, and records the pre-irradiation data pertaining to the finished fuel rods and fuel assembly. Irradiation of the fuel assembly in the VBWR was initiated on July 17, 1962.

Summary: Stainless steel clad nuclear fuel cycle costs can be reduced to those associated with Zircaloy clad fuel or potentially lower by reducing the thickness of the clad tube wall until performance penalties offset the savings associated with the reduction in parasitic neutron absorption. To demonstrate the feasibility and investigate performance capabilities of thin clad fuel rods for power reactor application an assembly was fabricated with 0.0127 cm (5 mil) thick stainless steel cladding tubes for irradiation testing in the Vallecitos Boiling Water Reactor (VBWR). The fuel bundle was placed in the VBWR and irradiation was begun in November, 1961. The irradiation is scheduled to continue until the target exposure of 2.74 x 10(20) fissions/cc (10,000 MWD/T of uranium) average burnup is reached. Destructive examinations of fuel rods will be performed at regular intervals throughout life to determine fuel rod performance.

Report issued by the Atomic Energy Commission over studies conducted on the determination of cerium-144 in vegetation and soil. Materials and methods used in the determination are discussed. This report includes tables, and an illustration.

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The corrosion of 8081 and X-8001 aluminum alloys and the resultant formation of an adherent corrosion product on the corroding surface were investigated under conditions (except radiation) comparable to those that will exist on the surface of fuel-element cladding during operation of the Advanced Test Reactor. Since previous experiments indicated that corrosion penetration of the aluminum clad was unlikely during a reactor cycle provided the water chemistry is properly controlled, most of the studies in this investigation were concerned with the effect of variables on the rate of formation of corrosion- product films. These films have low thermal conductivity and can be a major factor in producing high fuel-element temperatures which lead to fuel-plate instabilities. The experimental procedures were the same as used in a similar study for the High Flux Isotope Reactor, but the ranges of variables investigated were greater than in previous studies. The 6061 and X-8001 alloys corroded to the same extent under the same test conditions until the corrosion product (boehmite) that formed on the surface bccame thick enough to spall spontaneously from the surface, usually about 2 mils thick. Spallation from the surface of the 6061 alloy was always accompanled by localized attack of the …

Intergranular cracking of Type 304 stainless steel outlet nozzles in reactor moderator service prompted a broad program of laboratory studies to determine the cause of the failures. It was demonstrated that sensitized and pickled Type 304 stainless steel is extremely susceptible to both intergranular and transgranular chloride stress corrosion cracking in hot water of pH 4.5 to 5.0 which contains as little as 2 ppM chloride ion. Although the chloride content of moderator is only about 0.01--0.03 ppM, it was concluded that chloride concentrations sufficient to cause cracking occurred on the nozzle surfaces, either very gradually or as a result of a system change. This conclusion was substantiated later when chlorides were shown to be concentrated in a film of aluminum oxide (from fuel cladding corrosion) deposited on the moderator side of a failed nozzle. Circumstantial evidence suggested that initiation of moderator pH (pD) control with nitric acid and oxygen caused or contributed to cracking of the nozzles. Therefore, in recent laboratory work the effects of pH and oxygen concentration on cracking of sensitized and pickled Type 304 stainless steel were investigated. The effects of nitrate and sulfate ion concentrations were also investigated. Results of these laboratory investigations are summarized …

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This book is a revision of "The Effects of Nuclear Weapons" which was issued in 1957. It was prepared by the Defense Atomic Support Agency of the Department of Defense in coordination with other cognizant governmental agencies and was published by the U.S. Atomc Energy Commission. Although the complex nature of nuclear weapons effects does not always allow exact evaluation, the conclusions reached herein represent the combined judgment of a number of the most competent scientists working the problem. There is a need for widespread public understanding of the best information available on the effects of nuclear weapons. The purpose of this book is to present as accurately as possible, within the limits of national security, a comprehensive summary of this information.

Technical report. From Abstract : "A number of the physical properties from which we can obtain both direct and indirect information concerning the band structures of metals, have been measured for most of the rare earth metals. It was thought that it would be desirable to review ans examine these data and try to tie them together. For this purpose the very low and room temperature heat capacities, Hall coefficients, magnetic susceptibilities, spectral data and electrical resistivities were examined."

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From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.