Radiolytic gas production during long-term storage of nuclear wastes

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Gases produced by in situ radiolysis of sealed solidified nuclear wastes during long-term storage could conceivably breach containment. Therefore, candidate waste forms (matrices containing simulated nuclear wastes) were irradiated with /sup 60/Co-..gamma.. and /sup 244/Cm-..cap alpha.. radiation. These forms were: cement containing simulated fission product sludges, vermiculite containing organic liquids, and cellulosics contaminated with ..cap alpha..-emitting transuranic isotopes. For cement waste forms exposed to ..gamma..-radiolysis, an equilibrium hydrogen pressure was reached that was dose rate dependent. For ..cap alpha..-radiolysis, equilibrium was not reached. With organic wastes (n-octane on vermiculite), H/sub 2/ and traces of CO/sub 2/ and CH/sub 4/ were ... continued below

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Pages: 25

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Bibler, N. E. January 1, 1976.

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Description

Gases produced by in situ radiolysis of sealed solidified nuclear wastes during long-term storage could conceivably breach containment. Therefore, candidate waste forms (matrices containing simulated nuclear wastes) were irradiated with /sup 60/Co-..gamma.. and /sup 244/Cm-..cap alpha.. radiation. These forms were: cement containing simulated fission product sludges, vermiculite containing organic liquids, and cellulosics contaminated with ..cap alpha..-emitting transuranic isotopes. For cement waste forms exposed to ..gamma..-radiolysis, an equilibrium hydrogen pressure was reached that was dose rate dependent. For ..cap alpha..-radiolysis, equilibrium was not reached. With organic wastes (n-octane on vermiculite), H/sub 2/ and traces of CO/sub 2/ and CH/sub 4/ were produced, and O/sub 2/ was consumed with both radiations. Only energy absorbed by the organic material was effective in producing H/sub 2/. At low dose rates with both ..cap alpha..- and ..gamma..-irradiations, G(H/sub 2/) was 4.5 and G(-O/sub 2/) was 5.0. Also, equilibrium was not obtained. For cellulosic material, H/sub 2/, CO/sub 2/, and CO were produced in the ratio of 1.0:0.7:0.3, and O/sub 2/ was consumed. With ..cap alpha..-radiolysis, G(gas) was dose dependent; measured values ranged from 2.2 to 0.6 as the dose increased. Implications of all these results on long-term storage of radioactive waste are discussed. Some data from an actual nuclear wasteform are also presented.

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Pages: 25

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Dep. NTIS

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  • 28. southeastern regional meeting of American Chemical Society on biological applications of liquid chromatography, Gatlinburg, TN, USA, 27 Oct 1976

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  • Report No.: DP-MS-76-51
  • Report No.: CONF-761002-3
  • Grant Number: E(07-2)-1
  • Office of Scientific & Technical Information Report Number: 7348224
  • Archival Resource Key: ark:/67531/metadc1445338

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  • January 1, 1976

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  • Feb. 10, 2019, 8:45 p.m.

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Bibler, N. E. Radiolytic gas production during long-term storage of nuclear wastes, article, January 1, 1976; United States. (https://digital.library.unt.edu/ark:/67531/metadc1445338/: accessed April 23, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.