Abstract
In 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 HNO3 solution. However, Ba crystallized as Ba(NO3)2 and the washing was ineffective for the decontamination of Ba. High HNO3 and Pu concentrations in the mother liquor, the decontamination factor (DF) of Cs was low because Cs precipitated with Pu as Cs2Pu(NO3) 6. The Pu clearly showed a reasonable DF because the amount of Pu in the dissolver solution was higher than that of Cs. Almost all the amount of Pu remains in the mother liquor except the one in the Cs2Pu(NO 3)6 precipitate.
| Original language | English |
|---|---|
| Pages (from-to) | 315-320 |
| Number of pages | 6 |
| Journal | Radiochimica Acta |
| Volume | 98 |
| Issue number | 6 |
| DOIs | |
| Publication status | Published - 2010 Jun |
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ASJC Scopus subject areas
- Physical and Theoretical Chemistry
Cite this
Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal. / Nakahara, M.; Nomura, K.; Washiya, T.; Chikazawa, T.; Hirasawa, Izumi.
In: Radiochimica Acta, Vol. 98, No. 6, 06.2010, p. 315-320.Research output: Contribution to journal › Article
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TY - JOUR
T1 - Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal
AU - Nakahara, M.
AU - Nomura, K.
AU - Washiya, T.
AU - Chikazawa, T.
AU - Hirasawa, Izumi
PY - 2010/6
Y1 - 2010/6
N2 - In 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 HNO3 solution. However, Ba crystallized as Ba(NO3)2 and the washing was ineffective for the decontamination of Ba. High HNO3 and Pu concentrations in the mother liquor, the decontamination factor (DF) of Cs was low because Cs precipitated with Pu as Cs2Pu(NO3) 6. The Pu clearly showed a reasonable DF because the amount of Pu in the dissolver solution was higher than that of Cs. Almost all the amount of Pu remains in the mother liquor except the one in the Cs2Pu(NO 3)6 precipitate.
AB - In 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 HNO3 solution. However, Ba crystallized as Ba(NO3)2 and the washing was ineffective for the decontamination of Ba. High HNO3 and Pu concentrations in the mother liquor, the decontamination factor (DF) of Cs was low because Cs precipitated with Pu as Cs2Pu(NO3) 6. The Pu clearly showed a reasonable DF because the amount of Pu in the dissolver solution was higher than that of Cs. Almost all the amount of Pu remains in the mother liquor except the one in the Cs2Pu(NO 3)6 precipitate.
UR - http://www.scopus.com/inward/record.url?scp=77956128470&partnerID=8YFLogxK
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U2 - 10.1524/ract.2010.1732
DO - 10.1524/ract.2010.1732
M3 - Article
VL - 98
SP - 315
EP - 320
JO - Radiochimica Acta
JF - Radiochimica Acta
SN - 0033-8230
IS - 6
ER -