Quarterly Progress Report for the Period July 1 to September 30, 1958

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An evaluation and the resulting conclusions of work performed are given for each project in which definitive progress was made. The principle progress consisted of: obtaining promising fuel fabrication results from production scale investigations of simplified UO/sub 2/ preparations methods, presintering operation elimination, increasing pellet densities and reductions of UO/sub 2/ losses; successfully brazing a ninety-five inch long experimental fuel subassembly in which all joints, including outside ferrules and control rod rubbing strips, had brazed fillets; completing the fabrication of the last group of MTR process water irradiation samples and all of the in-pile test loop samples except for the ... continued below

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Pages: 113

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Garbe, R. W. & Walchli, H. E. October 31, 1959.

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Description

An evaluation and the resulting conclusions of work performed are given for each project in which definitive progress was made. The principle progress consisted of: obtaining promising fuel fabrication results from production scale investigations of simplified UO/sub 2/ preparations methods, presintering operation elimination, increasing pellet densities and reductions of UO/sub 2/ losses; successfully brazing a ninety-five inch long experimental fuel subassembly in which all joints, including outside ferrules and control rod rubbing strips, had brazed fillets; completing the fabrication of the last group of MTR process water irradiation samples and all of the in-pile test loop samples except for the specimens containing 27% enriched pellets; performing a nuclear analysis of various fuel assembly designs as part of an over-all evaluation of fuel assembly bowing in the Yankee reactor; completing corrosion studies of primary plant materials in static autoclaves to aid in the selection of a pH control agent; developing a Compromise Design'' for the fueh assembly which incorporates a series of small design changes to eliminate the possibility of restricting control rod motion by interference due to a superposition of bowing of the fuel assembly and an adverse accummulation of mechanical tolerances; completing the calculation of the moderator temperature coefficient, the Doppler temperature coefficient, the void coefficient, neutron lifetime, and delayed neutron fraction; obtaining flux profiles, flux peaking, flux spectrum, peripheral fuel rod worth, void coefficient, temperature coefficient, and control rod worth data from the Critical Reactor Experiments with a 3: 1 water-to-uranium metal ratio core at the Westinghouse Reactor Evaluation Center; continuing instrumentation and individual component operational testing of the in-pile test loop; and analyzing the results of the post-irradiation examination of the second group of process water samples and delivery of the last group of samples to the MTR. (For preceding period see YAEC-87.) (auth)

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Pages: 113

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  • Other Information: For Yankee Atomic Electric Co. Orig. Receipt Date: 31-DEC-59

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  • Report No.: YAEC-97
  • Grant Number: AT(30-3)-222, SUBCONTRACT NO. 1
  • DOI: 10.2172/4289488 | External Link
  • Office of Scientific & Technical Information Report Number: 4289488
  • Archival Resource Key: ark:/67531/metadc1017843

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Creation Date

  • October 31, 1959

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 17, 2018, 2:57 p.m.

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Garbe, R. W. & Walchli, H. E. Quarterly Progress Report for the Period July 1 to September 30, 1958, report, October 31, 1959; Pittsburgh, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc1017843/: accessed November 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.