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Volumn 42, Issue 1, 2007, Pages 39-43
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The effects of container materials and buffer additives on decreasing the iodide concentration in a disposal vault for spent nuclear fuel
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Author keywords
Additive; Bentonite; Iodine; Migration; Silver oxide; Sorption
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Indexed keywords
ACTIVATED CARBON;
ADDITIVES;
BENTONITE;
CONTAINERS;
COPPER ALLOYS;
CORROSION PROTECTION;
IODINE COMPOUNDS;
PORE SIZE;
PYRITES;
SILVER;
SORPTION;
SPENT FUELS;
CHALCOPYRITES;
DISPOSAL VAULT;
GALENA;
MIGRATION;
SILVER OXIDE;
NUCLEAR FUELS;
ALUMINUM SILICATE;
BENTONITE;
BUFFER;
CHALCOPYRITE;
COPPER;
IODIDE;
IRON;
LEAD SULFIDE;
NUCLEAR FUEL;
PYRITE;
SILVER;
SILVER DERIVATIVE;
ARTICLE;
CONCENTRATION (PARAMETERS);
CONTAINER;
CORROSION;
PARTICLE SIZE;
POROSITY;
PRECIPITATION;
RADIOACTIVE WASTE DISPOSAL;
BUFFERS;
IODIDES;
NUCLEAR ENERGY;
RADIATION PROTECTION;
RADIOACTIVE WASTE;
REFUSE DISPOSAL;
WASTE MANAGEMENT;
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EID: 33845305846
PISSN: 10934529
EISSN: 15324117
Source Type: Journal
DOI: 10.1080/10934520601015461 Document Type: Article |
Times cited : (2)
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References (14)
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