The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.

The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.

From abstract: "A preliminary design is presented for a boiling water reactor power plant for a propulsion of a 22,000 SHP commercial tanker."

From introduction: "The purpose of the report is to set forth the development philosophy, objectives and expected results of the AEC-GE Nuclear Superheat Project."

From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."

Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.

From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."

Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.

Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.

Report describing the Hanford Plutonium Recycle Test Reactor (PRTR), its building, safety procedures, site, operations, and analyses of its safety features.

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.

Report that presents and interprets data taken from previous tests involving gas-lift circulators and then correlates the data for the purpose of design and operational improvements.

Report describing the development and installation of an automated conveyor-type laundry system for the purpose of monitoring laboratory clothing for beta-gamma contamination.

Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).

Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).

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.

Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.

Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.

Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)

Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.

"The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."