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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Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: 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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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. 
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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. 
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