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Title: HOT-CELL EVALUATION OF THE RELEASE OF TRITIUM AND $sup 85$Kr DURING PROCESSING OF ThO$sub 2$-UO$sub 2$ FUELS

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn.
OSTI Identifier:
4530121
Report Number(s):
ORNL-3956
NSA Number:
NSA-20-031447
DOE Contract Number:
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-66
Country of Publication:
United States
Language:
English
Subject:
HEALTH AND SAFETY

Citation Formats

Goode, J.H. HOT-CELL EVALUATION OF THE RELEASE OF TRITIUM AND $sup 85$Kr DURING PROCESSING OF ThO$sub 2$-UO$sub 2$ FUELS. United States: N. p., 1966. Web. doi:10.2172/4530121.
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Goode, J.H. HOT-CELL EVALUATION OF THE RELEASE OF TRITIUM AND $sup 85$Kr DURING PROCESSING OF ThO$sub 2$-UO$sub 2$ FUELS. United States. doi:10.2172/4530121.
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Goode, J.H. Wed . "HOT-CELL EVALUATION OF THE RELEASE OF TRITIUM AND $sup 85$Kr DURING PROCESSING OF ThO$sub 2$-UO$sub 2$ FUELS". United States. doi:10.2172/4530121. https://www.osti.gov/servlets/purl/4530121.
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@article{osti_4530121,
title = {HOT-CELL EVALUATION OF THE RELEASE OF TRITIUM AND $sup 85$Kr DURING PROCESSING OF ThO$sub 2$-UO$sub 2$ FUELS},
author = {Goode, J.H.},
abstractNote = {},
doi = {10.2172/4530121},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jun 01 00:00:00 EDT 1966},
month = {Wed Jun 01 00:00:00 EDT 1966}
}
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Technical Report:
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DOI:  10.2172/4530121
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  • - Trans. Amer. Nucl. Soc.

  • ; ;
    Fission gas release data are presented for five fuel rods irradiated at low fuel temperature (below 2700/sup 0/F) with burnups up to 90,000 MWD/MTM. Four of these rods contained ThO/sub 2/-UO/sub 2/ (33.6 weight percent UO/sub 2/) fuel pellets; the fifth rod contained ThO/sub 2/ pellets. These data supplement fission gas release information previously reported for 54 rods containing ThO/sub 2/-UO/sub 2/ and ThO/sub 2/ fuel, some of which experienced fuel temperaures up to 5000/sup 0/F and burnups to 56,000 MWD/MTM. These new data suggest that at burnups exceeding about 80,000 MWD/MTM a sharp increase in fission gas release occurs,more » possibly caused by microstructural changes in the fuel. This is similar to the behavior of UO/sub 2/ except that the increase occurs in UO/sub 2/ at lower burnup (approximately 40,000 MWD/MTM). The fission gas release calculational model previously reported has been modified to account for the observed increase in the low temperature component. The revised model provides a good best estimate of all the fission gas release data.« less

  • 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, andmore » 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)« less

  • ; ; ; ...
    Fission gas release data are presented from 51 fuel rods irradiated as part of the LWBR irradiations test program. The fuel rods were Zircaloy-4 clad and contained ThO/sub 2/ or ThO/sub 2/-UO/sub 2/ fuel pellets, with UO/sub 2/ compositions ranging from 2.0 to 24.7 weight percent and fuel densities ranging from 77.8 to 98.7 percent of theoretical. Rod diameters ranged from 0.25 to 0.71 inches and fuel active lengths ranged from 3 to 84 inches. Peak linear power outputs ranged from 2 to 22 kw/ft for peak fuel burnups up to 56,000 MWD/MTM. Measured fission gas release was quite low,more » ranging from 0.1 to 5.2 percent. Fission gas release was higher at higher temperature and burnup and was lower at higher initial fuel density. No sensitivity to UO/sub 2/ composition was evidenced.« less