MARC

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035 |a (TOE)ost6323597 
035 |a (TOE)6323597 
040 |a TOE  |c TOE 
049 |a GDWR 
072 7 |a 21  |2 edbsc 
072 7 |a 36  |2 edbsc 
086 0 |a E 1.99:ornl/tm-7674 
086 0 |a E 1.99:ornl/tm-7674 
088 |a ornl/tm-7674 
245 0 0 |a Performance of HTGR biso- and triso-coated fertile particles irradiated in capsule HT-34  |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. Department of Energy,  |c 1981. 
300 |a Pages: 71 :  |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 08/01/1981. 
500 |a "ornl/tm-7674" 
500 |a "DE81030430" 
500 |a Long, E.L. Jr.; Tiegs, T.N.; Robbins, J.M.; Kania, M.J. 
520 3 |a Experiment HT-34, irradiated in the target region of the High Flux Isotope Reactor (HFIR), was designed to correlate HTGR Biso- and Triso-coated particle performance with fabrication parameters. Gamma analysis of the irradiated Triso-coated ThO/sub 2/ particles showed that the SiC deposited at the highest coating rate apparently had the best cesium-retention properties. Results of a similar analysis of the irradiated Biso-coated ThO/sub 2/ particles showed no differences in performance that could be related to coating conditions, but all the particles showed a significant loss of cesium (> 50%) at the higher temperatures. Pressure-vessel failures occurred with a significant number of particles; however, fission-gas-content measurements made at room temperature showed that the intact Biso particles from all batches except one became permeable during irradiation. 
536 |b W-7405-ENG-26. 
650 7 |a Coated Fuel Particles.  |2 local. 
650 7 |a Performance Testing.  |2 local. 
650 7 |a Physical Radiation Effects.  |2 local. 
650 7 |a Htgr Type Reactors.  |2 local. 
650 7 |a Thorium Oxides.  |2 local. 
650 7 |a Burnup.  |2 local. 
650 7 |a Fission Products.  |2 local. 
650 7 |a Actinide Compounds.  |2 local. 
650 7 |a Chalcogenides.  |2 local. 
650 7 |a Fuel Particles.  |2 local. 
650 7 |a Gas Cooled Reactors.  |2 local. 
650 7 |a Graphite Moderated Reactors.  |2 local. 
650 7 |a Isotopes.  |2 local. 
650 7 |a Materials.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Oxygen Compounds.  |2 local. 
650 7 |a Radiation Effects.  |2 local. 
650 7 |a Radioactive Materials.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Testing.  |2 local. 
650 7 |a Thorium Compounds.  |2 local. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
650 7 |a Materials Science.  |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/scitech/biblio/6323597  |z Online Access (via OSTI) 
907 |a .b90533318  |b 03-09-23  |c 02-15-17 
998 |a web  |b 02-15-17  |c f  |d m   |e p  |f eng  |g    |h 0  |i 1 
956 |a Information bridge 
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952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99:ornl/tm-7674  |h Superintendent of Documents classification  |i web  |n 1