Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal
Keyword(s):
Mox Fuel
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AbstractIn order to examine the decontamination behavior of the Pu and fission products (FPs) that contained with the uranyl nitrate hexahydrate (UNH) crystals in the U crystallization process, experiments were carried out using mixed oxide (MOX) fuel dissolver solution. The experiments confirmed that Eu was adequately decontaminated by washing the UNH crystals with a HNO
2013 ◽
Vol 01
(01)
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pp. 55-60
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Keyword(s):
1999 ◽
Vol 273
(3)
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pp. 239-247
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Keyword(s):
2013 ◽
Vol 255
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pp. 132-137
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2000 ◽
Vol 307
(1-2)
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pp. 1-9
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Failure behavior of plutonium-uranium mixed oxide fuel under reactivity-initiated accident condition
1992 ◽
Vol 188
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pp. 154-161
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