MARC

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035 |a (TOE)ost6227750 
035 |a (TOE)6227750 
040 |a TOE  |c TOE 
049 |a GDWR 
072 7 |a 12  |2 edbsc 
086 0 |a E 1.99:conf-781121--13 
086 0 |a E 1.99:conf-781121--13 
088 |a conf-781121--13 
245 0 9 |a Disposal of Iodine-129  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Department of Energy. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1978. 
300 |a Pages: 8 :  |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 01/01/1978. 
500 |a "conf-781121--13" 
500 |a Annual meeting of Materials Research Society, Boston, MA, USA, 28 Nov 1978. 
500 |a Williams, C.; Newman, E.; Moore, J. G.; Morgan, M. T.; Devaney, H. E.; Rogers, G. C. 
520 3 |a One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative. 
536 |b W-7405-ENG-26. 
650 7 |a Iodine 129.  |2 local. 
650 7 |a Radioactive Waste Disposal.  |2 local. 
650 7 |a Leaching.  |2 local. 
650 7 |a Iodates.  |2 local. 
650 7 |a Marine Disposal.  |2 local. 
650 7 |a Underground Disposal.  |2 local. 
650 7 |a Beta Decay Radioisotopes.  |2 local. 
650 7 |a Concretes.  |2 local. 
650 7 |a Building Materials.  |2 local. 
650 7 |a Dissolution.  |2 local. 
650 7 |a Halogen Compounds.  |2 local. 
650 7 |a Intermediate Mass Nuclei.  |2 local. 
650 7 |a Internal Conversion Radioisotopes.  |2 local. 
650 7 |a Iodine Compounds.  |2 local. 
650 7 |a Iodine Isotopes.  |2 local. 
650 7 |a Isotopes.  |2 local. 
650 7 |a Management.  |2 local. 
650 7 |a Materials.  |2 local. 
650 7 |a Nuclei.  |2 local. 
650 7 |a Oxygen Compounds.  |2 local. 
650 7 |a Radioisotopes.  |2 local. 
650 7 |a Beta-Minus Decay Radioisotopes.  |2 local. 
650 7 |a Separation Processes.  |2 local. 
650 7 |a Waste Disposal.  |2 local. 
650 7 |a Odd-Even Nuclei.  |2 local. 
650 7 |a Waste Management.  |2 local. 
650 7 |a Years Living Radioisotopes.  |2 local. 
650 7 |a Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities.  |2 edbsc. 
710 2 |a Oak Ridge National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
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/6227750/  |z Online Access 
907 |a .b72153763  |b 03-07-23  |c 11-08-12 
998 |a web  |b 11-08-12  |c f  |d b   |e p  |f eng  |g    |h 9  |i 2 
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:conf-781121--13  |h Superintendent of Documents classification  |i web  |n 1