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The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a major controlling factor in the acoustic response pattern. It appears to effect both acoustic emission intensity and the point in the crack formation-growth sequence at which the main emission occurs. A concept has been developed for the prototype of a full scale monitor system. Hardware development is being limited to the analyzer portion of the system at this time because it is the part most significant to demonstrating feasibility of the intended application. Signal level and signal rate are both being investigated as possible parameters for evaluating acoustic emission data. Of the various transducers for potential high temperature application, the capacitive or electrostatic transducer now looks most promising. A significant improvement in sensitivity has been achieved and a trial model used during recent tests produced …

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This report discusses the objectives of the FFTF Fuel Handling and Radioactive Maintenance System Group which are: To remove and replace test components from the reactor core under a controlled environment to permit maximum acquisition and preservation of experimental data; to service and maintain the reactor core to enable maximum utilization of the irradiation capability of the facility; and to provide the radioactive maintenance capability consistent with the requirement for high plant factor and safety considerations.

This report provides source and special nuclear material composition of ending inventory reports for the month of September, 1966.

The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefaction wave pressures during high temperature, high pressure blowdown studies.

The Counting Handbook is a compilation of operational techniques and performance specifications on counting equipment in use at the Lawrence Radiation Laboratory, Berkeley. Counting notes have been written from the viewpoint of the user rather than that of the designer or maintenance man. The only maintenance instructions that have been included are those that can easily be performed by the experimenter to assure that the equipment is operating properly.

One of two major facilities used for plutonium fuels research and development studies at Battelle-Northwest is the Plutonium Fuels Laboratory (PFL). This facility was specifically designed and equipped for research and development studies involving multikilogram quantities of plutonium and its mixtures, compounds, and alloys. As at other sites, the design and operation philosophy of the PFL is one of complete plutonium containment. Primary plutonium containment is provided by glove boxes, secondary containment is provided by individual laboratories, and tertiary containment is supplied by the building proper. Air samples, taken throughout the facility, are constantly being monitored for free contamination. Personnel exposure caused by X, gamma, and neutron radiation has been primarily omitted by inspiring good work habits and housekeeping practices in personnel (i.e., uncontrolled accumulations of plutonium are avoided, plutonium is confined as much as possible, exposure times are limited, and shielding equipment is used whenever necessary). Rules for the prevention of an inadvertent criticality in the PFL are based upon the criteria that at least two control conditions must fail before criticality is imminent.

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From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.

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The ultimate objectives of the Compact Thermoelectric Converter Program are to develop and qualify for space applications a reliable, high performance thermoelectric module and, if required, other converter hardware for use in 1 to 20 kilowatt (electric) compact thermoelectric converters.

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A study of relative plutonium and orallay values is being made by representatives of the production sites under direction of AEC Headquarters. Division of Production. (Oralloy is uranium enriched to 93-15 percent U-235.) Under study assumptions that will be detailed later, oralloy would cost less than formerly, and may be cheap enough to enrich production reactor discharged uranium to reactor input assays. To date uranium recycle enriching assays have been held below two percent U-235 -- usually 1.2 to 1.5. Use of orallay for enriching reactor tails would conserve U-236. which would increase neptunium and Pa-238 production. There may be other profitable reactor uses for the cheaper oralloy.The intent of this document is to give the oralloy cost data to those who may study or evaluate oralloy use, and to explain the basis for oralloy cost so that the validity of any use may be assessed.

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