Abstract: "This is the first interim report of a literature survey investigating the uses and technology of radioscopes in the countries of the world, with particular emphasis necessarily placed on those more highly industrialized nations. Part I includes a general summary of the quantity and quality of radioisotope work being performed in these countries. Among the outstanding radioisotope applications with respect to quantity is the work of Japan in chemical research, that of USSR in metals research, and that in the USA in medical research. A detailed qualitative examination of the relatively narrow region of radioisotope applications in leak detection is also presented. Part II of this report gives a direct comparison between the progress and status of the US and the USSR in the varied uses of radio-isotopes."

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This document details activities of the irradiation processing department during the month of July 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; Financial Operation; and NPR Project.

This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

A summary of HAPO activities is given to include separate sections on the N-Reactor and other current production reactors. Specific programs and fuel performance for current production reactor fuels is discussed. Also, the production status, fuel performance, development program and process technology for N-Reactor fuels is presented.

This report details reactor incidents from August 5, 1958 through August 14, 1967.

Since start-up of the neptunium recovery and purification program at HAPO, the neptunium-has been subjected to the following process steps: Production of crude neptunium nitrate by the Redox and Purex plants; Production of purified neptunium nitrate, using an anion exchange process, in research and development facilities operated by CPD`s Process Chemistry Operation; Production of neptunium oxide (NpO{sub 2}) by Process Chemistry. Mixing the NpO{sub 2} powder with aluminum powder and incorporation in an aluminum-clad-target element, done by the Plutonium Metallurgy Operation of Hanford Laboratories; and Irradiation of the target elements in the Savannah River reactors; and Chemical reprocessing of the irradiated target elements at Savannah River to recover the desired plutonium-238 and the unconverted neptunium. As frequently happens to between-contractor transfers, neptunium material balances between Hanford`s NpO{sub 2} and Savannah River`s recovered neptunium have sometimes been poorer than expected. Because of wide spread interest in this problem, it was deemed desirable to put on record a description of the measurement techniques which have been used at Hanford for NpO{sub 2} and the improvements which have been made in the analytical methods. The measurement methods used for purified nitrate are also described.

Figures are included which gives the necessary information on C Reactor for analysis of stress buildup in the graphite tube blocks.

Presently, there is no standard technique in use by all assigned physicists to actually calculate required reactor loading changes. Basically, loading changes are made by determining the number of enrichment columns needed for equilibrium operation following startup; this is usually based upon past experience with relatively similar reactor conditions. Selection of locations for placement or removal of the enrichment then involves the application of information gleaned from temperature maps, previous experience, educated guesses, or a combination of the three. The program is based on one-group, one-dimensional, diffusion theory. Local buckling effects caused by fission products, temperatures, and materials are calculated for many small zones of the reactor before and after a discharge. Loading changes are then designed to produce a central zone buckling of zero with the required supporting buckling of the enrichment ring; equal bucklings for all zones within a particular region are achieved by manipulation of the enrichment inventory in each particular zone. This program is primarily designed for specific use by assigned physicists of the Pile Physics unit. Basic familiarity with the standard calculational techniques, nomenclature, and technical jargon of that group is necessary for effective application. Program input includes region geometry and material, plus reactivity variables; …

The purpose of this report is to provide a basic working tool for determining the relationship between the allowable temperature increase within the Columbia River reach at the Hanford Site and the actual temperature increase as associated with various reactor operating modes. This basic tool can be utilized for day-to-day operating purposes or for the achievement of historical information.

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This report deals with the use of violence as a political technique covers the major book and periodical literature on this subject produced over the past ten years.

This report addresses a survey of background and legal problems.

This document details activities of the irradiation processing department during the month of July 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations: Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

A survey of the character and magnitude of hazards involved in processing liquid metal bonded fuels was made and the scope of a preliminary experimental program outlined. Processing of SRE and CPPD fuels by mechanical decladding followed by controlled reaction of the collected methods. Simdlarly, shearing of PRDC fuel and controlled exposure of the Na in the severed portions to water appears more desfrable than chethical dissolution of the metallic cladding. (auth)

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