A stress analysis of the 3/8-inch and 1/4-inch pins which hold the rake assembly to the flange was performed and shows stresses to be lower than the Class 1 allowables of the ASME Boiler and Pressure Vessel Code. The alternating pin stresses were found to be below the endurance limit and fatigue failure will not occur. The rake assembly was assumed to be loaded by steady drag and lift forces and alternating vortex shedding forces.

The objective of this presentation is to: (1) present the physical motivation for fusion-fission hybrids, (2) outline design considerations for hybrid blankets, and (3) discuss the nuclear performance potential of hybrid blankets.

Gas quality results obtained at LLL on samples taken from the three nuclear gas-well-stimulation experiments (Gasbuggy, Rulison, Rio Blanco) are used to illustrate the differences and similarities of the three projects. All of the gas analysis data shown here have been previously published in LLL reports, but heretofore, intercomparisons have been difficult because of the different formats used in the various publications. Also, the data from the three expriments have not previously been manipulated in the same way so that postshot conditions in the three cavity and chimney systems could be compared. As the pressure and temperature increase in the cavity and chimney system (as they do with increasing depth of burial) the amount of water produced with the chimney gas increases markedly. Differences in late-time additions of CO/sub 2/ to the chimney gas were also observed. Previously reported radiological safety studies of the potential effects from the use of nuclearly stimulated gas are discussed, and the required steps that could lead to the possible sale of nuclearly stimulated gas to the general public are listed.

The elevated temperature fatigue-crack propagation response of Inconel 600 and Inconel 718 was characterized within a linear-elastic fracture mechanics framework in air and low-oxygen liquid sodium environments. The crack growth rates of both nickel-base alloys tested in liquid sodium were found to be considerably lower than those obtained in air. This enhanced fatigue resistance in sodium was attributed to the very low oxygen content in the inert sodium environment. Electron fractographic examination of the Inconel 600 and Inconel 718 fatigue fracture surfaces revealed that operative crack growth mechanisms were dependent on the prevailing stress intensity level. Under low growth rate conditions, Inconel 600 and Inconel 718 fracture surfaces exhibited a faceted, crystallographic morphology in both air and sodium environments. In the higher growth rate regime, fatigue striations were observed; however, striations formed in sodium were rather ill-defined. These indistinct striations were attributed to the absence of oxygen in the liquid sodium environment. Striation spacing measurements were found to be in excellent agreement with macroscopic growth rates in both environments.

Results are summarized of the combined efforts of the Division of Industrial Energy Conservation (INDUS) and independent reviewers to perform an evaluation of the existing and proposed INDUS energy conservation research, demonstration, and development projects. The purpose of the review was to obtain evaluations of the capital cost, energy savings, and operating costs for each project which would be used to upgrade the original proposal data currently in the threshold system. Section II contains the detailed summaries of the threshold evaluation data prepared by the members. Section III contains the risk analysis data submitted by the reviewers. (MCW)

Objectives were to review the Annular Linear Induction Pump (ALIP) concept and program status, determine the desirability for such a concept for large scale plant Main Heat Transport systems, and establish the extent of interest and support for preceeding with development.

The progress to date for each major element of the program is graphed. A description of each program element is given. Completion of the data acquisition system has slipped due to a delay in delivery from Hewlett Packard. Part of the labor costs allocated for this includes time for personnel to become familiar with the equipment and to integrate the system with the test set-up. Completion of the test cell and the fuel system has slipped. This has turned out to be a significant undertaking and is being paced by the three contractors supplying the plumbing, air conditioning and fuel tank. Completion of each is now scheduled for March 1, and no slippage in the completion of the exhaust gas simulator is anticipated. The other element underway is a pilot model of the two-stage deaeration system. This work is briefly described.

Recently a preliminary program at Savannah River Plant was began to measure I-129 concentrations in a variety of environmental samples. The objectives of the study were three-fold: First, to at least qualitatively estimate the impact of Savannah River Plant (SRP) operations on the I-129 inventory in the surrounding area; second, to determine prominent pathways of I-129 to man and to obtain, where possible, estimates of their associated dose rates; and third, to provide necessary input data to help in the design and implementation of more comprehensive follow-up studies.

From surface effects in controlled thermonuclear fusion devices and reactors meeting; Argonne, Illinois, USA (10 Jan 1974). A conceptual D-T fusion reactor employing magnetic mirror confinement and periodic focusing electrostatic direct conversion is described with emphasis on surface conditions. (auth)

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The sensitivities of district heating costs to various design parameters are explored. Some recent studies evaluating the economics of district heating are briefly summarized. The bases and methods for the cost and design sensitivity studies are outlined. Cost and design relationships are examined. These relationships are developed as part of a design study for a city with a population of 175,000. Use of a specific city as a basis for these studies shows the importance of site specific factors in the development of the best district heating design for the city. The problems of utilizing the delivered water are briefly reviewed. Some alternatives system designs are compared in terms of economics, energy efficiency, and their potential for widespread application. (MHR)

The Program Plan represents the top level guidance document for stating and performing the objectives of the Decontamination and Disposition (D and D) Program. The program objectives, historical data, and program description are presented, along with the top level planning. The planning includes a statement of the funding basis and the corresponding first and second level activity network schedules. The management plan is included which describes the procedures to be used for cost and schedule control and reporting, purchasing and subcontract control, and program and engineering data control. The requirements for the quality assurance plan, operational safety plan, and training plan are presented.

Several tritium recovery and purification techniques developed at non-production sites are described in the unclassified and declassified literature. Heating of irradiated Li-Al alloy under vacuum to release tritium is described in declassified reports of Argonne National Laboratory. Use of palladium membranes to separate hydrogen isotopes from other gases is described by Argonne, KAPL, and others. Declassified KAPL reports describe tritium sorption on palladium beds and suggest fractional absorption as a means of isotope separation. A thermal diffusion column for tritium enrichment is described in a Canadian report. Mound Laboratory reports describe theoretical and experimental studies of thermal diffusion columns. Oak Ridge reports tabulate ''shape factors'' for thermal diffusion columns. Unclassified journals contain many articles on thermal diffusion theory, experiments, and separation of gas mixtures by thermal diffusion columns; much of these data can be readily extended to the separation of hydrogen-tritium mixtures. Cryogenic distillation for tritium recovery is described in the Mound Laboratory reports. Process equipment such as pumps, valves, Hopcalite beds, and uranium beds are described in reports by ANL, KAPL, and MLM, and in WASH-1269, Tritium Control Technology.

This study of the feasibility of further automating the Central Laboratories deals specifically with the combined laboratory operations in Salt Lake City, Utah, and Denver, Colorado and is prepared with the understanding that such a system will also be implemented at the Central Laboratories in Atlanta, Georgia, and Albany, New York. The goals of automation are defined in terms of the mission of a water analysis laboratory, propose alternative computer systems for meeting such goals, and evaluate these alternatives in terms of cost effectiveness and other specified criteria. It is found that further automation will be beneficial and an in-house system that incorporates dual minicomputers is recommended: one for time-shared data acquisition, processing, and control; the second for data management. High-use analytical instruments are placed on-line to the time-shared minicomputer, with a terminal at each instrument and backup data storage on magnetic tape. A third, standby computer is switched in manually should the time-shared computer go down. Field-proven, modular hardware and software are chosen. Also recommended is the incorporation of the highly developed, computer-integrated instruments that are commercially available for determining petrochemicals and other organic substances, and are essential to the Laboratories' mission. (auth)