FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962

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The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiation of the second capsule is to be terminated so that it can serve as a control. Fabrication ... continued below

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Pages: 41

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Creator: Unknown. June 1, 1962.

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The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiation of the second capsule is to be terminated so that it can serve as a control. Fabrication was initiated on enriched UO/sub 2/ pellets for incorporation in full scale fuel rods to be irradiated in the Vallecitos Boiling Water Reactor. A wet nitrogen pyrohydrolysis step in conjunction with oxidationreduction cycling is being used to attain a satisfactory density exceeding 95% of theoretical at 1150 deg C. Apparatus and procedures being used for measurement of thermal conductivity and thermal expansion of sintered and cast uranium carbide are described. The coefficient of linear thermal expansion for a single specimen of 4.37 wt.% carbon sintered uranium carbide was determined to be 11.8 x 10/sup -6/ mm/mm- deg C, while that for a cast uranium carbide specimen containing 4.73 wt.% carbon was 10.6 x 10/sup -6/ mm/mm- deg C over the range from room temperature to l000 deg C. Hardness data for 4.4 and 4.8 plus or minus 0.1 wt.% carbon sintered and cast uranium carbide and for 5.2 wt.% carbon cast material are also presented. Irradiation test specimens previously prepared were given a pre-irradiation examination and were encapsulated. Three capsules, two using a sodium bond between fuel and container and one using an interference fit between fuel and container, were loaded in the MTR and appear to be operating under the required conditions. (auth)

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Pages: 41

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  • Other Information: Orig. Receipt Date: 31-DEC-62

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  • Report No.: UNC-5015
  • Grant Number: AT(30-1)-2374
  • DOI: 10.2172/4772538 | External Link
  • Office of Scientific & Technical Information Report Number: 4772538
  • Archival Resource Key: ark:/67531/metadc1059430

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  • June 1, 1962

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Jan. 25, 2018, 4:25 p.m.

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FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962, report, June 1, 1962; United States. (digital.library.unt.edu/ark:/67531/metadc1059430/: accessed August 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.