THE RELEASE OF Kr$sup 85$ FROM UO$sub 2$ IN ORR CAPSULES

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In an attempt to determine the validity of the method of predicting the release of fission gases from U0/sub 2/ suggested recently by Cottrell et al., a series of calculations were made of the expected release of Kr/sup 85/ from prototype Experimental Gas-Cooled Reactor (EGCR) fuel capsule irradiated in the Oak Ridge Research Reactor (ORR). The computed values were then compared with measured values of the per cent Kr/sup 85/ released. In the calculations, the thermal conductivity of the U0/sub 2/ was assumed to be 0.028 w/cm- deg C in the temperature range from 700 to 1600 deg C, and ... continued below

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Pages: 17

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Scott, J.L. October 1, 1961.

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In an attempt to determine the validity of the method of predicting the release of fission gases from U0/sub 2/ suggested recently by Cottrell et al., a series of calculations were made of the expected release of Kr/sup 85/ from prototype Experimental Gas-Cooled Reactor (EGCR) fuel capsule irradiated in the Oak Ridge Research Reactor (ORR). The computed values were then compared with measured values of the per cent Kr/sup 85/ released. In the calculations, the thermal conductivity of the U0/sub 2/ was assumed to be 0.028 w/cm- deg C in the temperature range from 700 to 1600 deg C, and in the absence of a precise knowledge of the helium gap, the cases of a 3-mil helium gas and no gap were treated. Values of the release-rate parameter (D) were estimated from BET surface areas of the U0/sub 2/ pellets. Results showed that the measured values of the per cent Kr/sup 85/ released generally fell within or close to the limits set by the 3-mil helium gap and no gap conditions. There was also a definite correlation between the measured values and the 3-mil gap condition when the clad temperature was about 700 deg C. When the clad temperature was about 800 deg C, the measured values corresponded better to the no gap condition. The correspondence between measured values and the calculated range lends evidence to the methed of Cottrell et al. as well as the value of the thermal conductivity of U0/sub 2/ used in the calculations. In addition, the sunface area of pressed and sintered UO/sub 2/ appears to be indicative of the D value for irradiated material at least up to 2400 Mwd/MT of U0/sub 2/. (auth)

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Pages: 17

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  • Other Information: Orig. Receipt Date: 31-DEC-61

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  • Report No.: ORNL-3195
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4833426 | External Link
  • Office of Scientific & Technical Information Report Number: 4833426
  • Archival Resource Key: ark:/67531/metadc1055822

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  • October 1, 1961

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 3:22 p.m.

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Scott, J.L. THE RELEASE OF Kr$sup 85$ FROM UO$sub 2$ IN ORR CAPSULES, report, October 1, 1961; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1055822/: accessed April 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.