Gaseous fission product release during storage at various temperatures for HTGR-type fuels [electronic resource]
Measurements were made of gaseous fission product releases from an HTGR-type fuel body under conditions simulating storage at temperatures up to 300°C. The fuel was a recycle test element containing BISO-BISO coated fuel particles which had been irradiated for 701 effective full-power days in the Pe...
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Online Access |
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Format: | Government Document Electronic eBook |
Language: | English |
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Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1978.
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Subjects: |
MARC
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245 | 0 | 0 | |a Gaseous fission product release during storage at various temperatures for HTGR-type fuels |h [electronic resource] |
260 | |a Oak Ridge, Tenn. : |b Oak Ridge National Laboratory. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1978. | ||
300 | |a Pages: 44 : |b digital, PDF file. | ||
336 | |a text |b txt |2 rdacontent. | ||
337 | |a computer |b c |2 rdamedia. | ||
338 | |a online resource |b cr |2 rdacarrier. | ||
500 | |a Published through SciTech Connect. | ||
500 | |a 07/01/1978. | ||
500 | |a "ornl/tm-6409" | ||
500 | |a Fitzgerald, C.L.; Vaughen, V.C.A.; Shannon, R.J. | ||
520 | 3 | |a Measurements were made of gaseous fission product releases from an HTGR-type fuel body under conditions simulating storage at temperatures up to 300°C. The fuel was a recycle test element containing BISO-BISO coated fuel particles which had been irradiated for 701 effective full-power days in the Peach Bottom HTGR. Storage test temperatures were ambient (about 30°C), 100, 150, 200, and 300°C. The initial release rates of ⁸⁵Kr varied after each change in temperature. A fairly stable release rate was reached that increased from approximately 60 ..mu..Ci/day at ambient temperature to approximately 1000 ..mu..Ci/day after 30 days at 200°C and slowly decreased to about 200 ..mu..Ci/day after 554 days at 200°C. In the experiment at 300°C, a final release rate of 4000 ..mu..Ci/day was attained after 66 days. The releases of ⁸⁵Kr were followed for about two and one-half years. The stabilized release rates for ³H were approximately 0.02 ..mu..Ci/day at ambient temperature, approximately 0.750 ..mu..Ci/day at 200°C after 30 days, and 0.460 ..mu..Ci/day after 554 days. The final release rate at 300°C was about 30 ..mu..Ci/day after 66 days.Over the lifetime of the experiment, approximately 22% of the initial ⁸⁵Kr inventory was evolved and swept out, and approximately 4% of the initial ³H inventory was evolved and swept out. The activation energies calculated for the Kr and ³H evolution were approximately 7.8 kcal/mole and approximately 12.4 kcal/mole, respectively. | |
536 | |b W-7405-ENG-26. | ||
650 | 7 | |a Beta Decay Radioisotopes. |2 local. | |
650 | 7 | |a Beta-minus Decay Radioisotopes. |2 local. | |
650 | 7 | |a Graphite Moderated Reactors. |2 local. | |
650 | 7 | |a Coated Fuel Particles. |2 local. | |
650 | 7 | |a Even-odd Nuclei. |2 local. | |
650 | 7 | |a Isotopes. |2 local. | |
650 | 7 | |a Power Reactors. |2 local. | |
650 | 7 | |a Tritium. |2 local. | |
650 | 7 | |a Temperature Dependence. |2 local. | |
650 | 7 | |a Helium Cooled Reactors. |2 local. | |
650 | 7 | |a Peach Bottom-1 Reactor. |2 local. | |
650 | 7 | |a Htgr Type Reactors. |2 local. | |
650 | 7 | |a Thermal Reactors. |2 local. | |
650 | 7 | |a Fuel Particles. |2 local. | |
650 | 7 | |a Intermediate Mass Nuclei. |2 local. | |
650 | 7 | |a Krypton Isotopes. |2 local. | |
650 | 7 | |a Isomeric Transition Isotopes. |2 local. | |
650 | 7 | |a Odd-even Nuclei. |2 local. | |
650 | 7 | |a Reactors. |2 local. | |
650 | 7 | |a Krypton 85. |2 local. | |
650 | 7 | |a Enriched Uranium Reactors. |2 local. | |
650 | 7 | |a Spent Fuel Storage. |2 local. | |
650 | 7 | |a Fission Product Release. |2 local. | |
650 | 7 | |a Energy. |2 local. | |
650 | 7 | |a Hydrogen Isotopes. |2 local. | |
650 | 7 | |a Light Nuclei. |2 local. | |
650 | 7 | |a Nuclei. |2 local. | |
650 | 7 | |a Gas Cooled Reactors. |2 local. | |
650 | 7 | |a Activation Energy. |2 local. | |
650 | 7 | |a Years Living Radioisotopes. |2 local. | |
650 | 7 | |a Radioisotopes. |2 local. | |
650 | 7 | |a Hours Living Radioisotopes. |2 local. | |
650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
710 | 2 | |a Oak Ridge National Laboratory. |4 res. | |
710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
856 | 4 | 0 | |u http://www.osti.gov/servlets/purl/7068303/ |z Online Access |
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