DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, July 1 through September 30, 1962

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Characterization and sintering results indicate significant differences between UO/sub 2/--35 wt% PuO/sub 2/ and the compositions containing lesser (<20 wt %) amounts of PuO/sub 2/. PuO/sub 2/ has now also been prepared by plutonium hydroxide precipitation. Sintering studies have shown that satisfictory density is readily attained with these PuO/sub 2/ materials. Development of analytical chemistry procedures required for support of the fuel cycle program is continuing. The x-ray emission procedure developed for the determination of plutonium and uranium is now being used on a routine basis. In preparation for post- irradiation analysis, analytical chemistry effort is being directed towards the ... continued below

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Creator: Unknown. October 31, 1963.

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Characterization and sintering results indicate significant differences between UO/sub 2/--35 wt% PuO/sub 2/ and the compositions containing lesser (<20 wt %) amounts of PuO/sub 2/. PuO/sub 2/ has now also been prepared by plutonium hydroxide precipitation. Sintering studies have shown that satisfictory density is readily attained with these PuO/sub 2/ materials. Development of analytical chemistry procedures required for support of the fuel cycle program is continuing. The x-ray emission procedure developed for the determination of plutonium and uranium is now being used on a routine basis. In preparation for post- irradiation analysis, analytical chemistry effort is being directed towards the development of plutonium and cesium separation procedures suitable for hot cell- alpha box techniques. For the short-term irradiation test program, the characterization as to density, open porosity, and closed porosity of sintered pellets has been continued. Pellets of each composition and density level have also been set aside as library samples and for x-ray diffraction and metallographic examination. The mechanical packing studies using spherical UO/ sub 2/ particles have been extended to the use of small diameter tubes suitable for reactor fuel elements. Plasma torch spheroidization studies have been extended to the mixed oxide, UO/sub 2/--20 wt % PuO/sub 2/. It has been determined that fusion of this mixed oxide is more difficult than the pure PuO/ sub 2/ investigated previously. The capsules for the short-term irradiation tests are now ready for final encapsulation, and samples of the fuel materials are undergoing complete pre-irradiation examination and evaluation. The final testing of the apparatus for the measurement of the thermal conductivity of poor thermal conductors at high temperature is almost completed. A study has been initiated to determine the compatibility of UO/sub 2/-PuO/sub 2/ mixtures with cladding, moderator, and fuel diluent materials. The reactor physics and economics study of the effect of ZrO/sub 2/ dilution of PuO/sub 2/--UO/sub 2/ fuels in near-thermal converter reactors has been compieted. (R.J.S.)

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  • Other Information: Orig. Receipt Date: 31-DEC-63

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  • Report No.: NUMEC-P-102
  • Grant Number: AT(30-1)-2389
  • DOI: 10.2172/4754801 | External Link
  • Office of Scientific & Technical Information Report Number: 4754801
  • Archival Resource Key: ark:/67531/metadc1029890

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  • October 31, 1963

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  • Oct. 18, 2017, 7:39 a.m.

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  • Oct. 24, 2017, 7:41 p.m.

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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, July 1 through September 30, 1962, report, October 31, 1963; United States. (digital.library.unt.edu/ark:/67531/metadc1029890/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.