From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.

Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.

From foreword: This report provides a review of the Soviet and U.S. technical information systems.

From introduction: The study is essentially an economic evaluation of the construction and operation of nuclear power plants at several designated military installations where increased power generating capabilities of 5 to 40 mwe may be required by the Government during the period 1963 through 1970.

From introduction: The study is essentially an economic evaluation of the construction and operation of nuclear power plants at several designated military installations where increased power generating capabilities of 5 to 40 mwe may be required by the Government during the period 1963 through 1970.

"This report tells the lessons learned from the second refueling of the Shippingport Atomic Power Station."

Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.

The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.

The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.

A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review

Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.

Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.

Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."

Abstract: "A continuous countercurrent solvent extraction process utilizing dibutyl carbitol as the extractant has been developed for separating 210Po from large amounts of associated bismuth. Both laboratory and pilot plant data demonstrate the process is a suitable headend step in recovery of kilogram quantities of 210Po. Typically, the extraction process recovers over 98% of the 210Po, essentially free from bismuth (Bi DF>1500), in a dilute HNO3 solution suitable as a starting material for final concentration and purification steps."

This report follows a study that was made to develop comparative fuel cycle costs for nitride and carbide fuels in a 1000 MWe sodium-cooled fast-breeder reactor.

This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.

From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.

Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.

Report documenting the measuring of strontium-90 levels contained in the bones of children and adults of various age brackets across the United States.

Report documenting the survey of the U. S. Army Chemical Corps Schoo, Radiological Instruction Area, Fort Mclellan, Alabama. This survey measures radiation an d gamma-ray flux in an approximately one square mile area.

Report examining "[t]he effect of ground roughness, or surface irregularities, on the radiation field above ground which had been contaminated with fallout from the explosion in the atmosphere of a nuclear device (Smallboy Event)" (p. v).

Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.

Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.