Radiolytic gas production from tritiated water sorbed on molecular sieve [electronic resource]
Samples of 4 A molecular sieve containing 5, 20, and 35 wt % H/sub 2/O were irradiated in sealed containers in a /sup 60/Co ..gamma..-ray source. A previous study showed that the effects of tritium ..beta..-radiolysis can be closely simulated by /sup 60/Co ..gamma..-radiolysis. During radiolysis, th...
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Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Oak Ridge, Tenn. :
distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1977.
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Subjects: |
MARC
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245 | 0 | 0 | |a Radiolytic gas production from tritiated water sorbed on molecular sieve |h [electronic resource] |
260 | |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1977. | ||
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 07/12/1977. | ||
500 | |a "dpst-77-375" | ||
500 | |a Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab. | ||
520 | 3 | |a Samples of 4 A molecular sieve containing 5, 20, and 35 wt % H/sub 2/O were irradiated in sealed containers in a /sup 60/Co ..gamma..-ray source. A previous study showed that the effects of tritium ..beta..-radiolysis can be closely simulated by /sup 60/Co ..gamma..-radiolysis. During radiolysis, the pressure of the containers was monitored, and the gas composition was determined. Results indicated that H/sub 2/ was the only gas produced. O/sub 2/ in air sealed in the container was depleted by radiolysis. Final pressures depended on the amount of tritium and H/sub 2/O present. At low tritium and low water contents, the final pressures were low (15 psi for 7 curies tritium/g sieve and 20 wt % H/sub 2/O). The maximum initial 100-eV yield for H/sub 2/ was 0.3 molecules/100-eV. Based on these results, TA 2-880 concerning tritium waste storage can be revised to permit containers of tritiated water sorbed on molecular sieve to be accepted for safe storage. | |
536 | |b EY-76-C-01-0009. | ||
650 | 7 | |a Radioactive Waste Storage. |2 local. | |
650 | 7 | |a Tritium Oxides. |2 local. | |
650 | 7 | |a Autoradiolysis. |2 local. | |
650 | 7 | |a Adsorption. |2 local. | |
650 | 7 | |a Cobalt 60. |2 local. | |
650 | 7 | |a Gamma Radiation. |2 local. | |
650 | 7 | |a Gases. |2 local. | |
650 | 7 | |a Hydrogen. |2 local. | |
650 | 7 | |a Molecular Sieves. |2 local. | |
650 | 7 | |a Oxygen. |2 local. | |
650 | 7 | |a Production. |2 local. | |
650 | 7 | |a Radiation Sources. |2 local. | |
650 | 7 | |a Adsorbents. |2 local. | |
650 | 7 | |a Autolysis. |2 local. | |
650 | 7 | |a Beta Decay Radioisotopes. |2 local. | |
650 | 7 | |a Beta-Minus Decay Radioisotopes. |2 local. | |
650 | 7 | |a Chemical Radiation Effects. |2 local. | |
650 | 7 | |a Chemical Reactions. |2 local. | |
650 | 7 | |a Chemistry. |2 local. | |
650 | 7 | |a Cobalt Isotopes. |2 local. | |
650 | 7 | |a Cryogenic Fluids. |2 local. | |
650 | 7 | |a Decomposition. |2 local. | |
650 | 7 | |a Electromagnetic Radiation. |2 local. | |
650 | 7 | |a Elements. |2 local. | |
650 | 7 | |a Fluids. |2 local. | |
650 | 7 | |a Intermediate Mass Nuclei. |2 local. | |
650 | 7 | |a Internal Conversion Radioisotopes. |2 local. | |
650 | 7 | |a Ionizing Radiations. |2 local. | |
650 | 7 | |a Isomeric Transition Isotopes. |2 local. | |
650 | 7 | |a Isotopes. |2 local. | |
650 | 7 | |a Labelled Compounds. |2 local. | |
650 | 7 | |a Management. |2 local. | |
650 | 7 | |a Minutes Living Radioisotopes. |2 local. | |
650 | 7 | |a Nonmetals. |2 local. | |
650 | 7 | |a Nuclei. |2 local. | |
650 | 7 | |a Odd-Odd Nuclei. |2 local. | |
650 | 7 | |a Radiation Chemistry. |2 local. | |
650 | 7 | |a Radiation Effects. |2 local. | |
650 | 7 | |a Radiations. |2 local. | |
650 | 7 | |a Radioactive Materials. |2 local. | |
650 | 7 | |a Radioisotopes. |2 local. | |
650 | 7 | |a Radiolysis. |2 local. | |
650 | 7 | |a Sorption. |2 local. | |
650 | 7 | |a Storage. |2 local. | |
650 | 7 | |a Tritium Compounds. |2 local. | |
650 | 7 | |a Waste Management. |2 local. | |
650 | 7 | |a Waste Storage. |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. | |
650 | 7 | |a Radiation Chemistry, Radiochemistry, And Nuclear Chemistry. |2 edbsc. | |
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/5359358 |z Online Access (via OSTI) |
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