Abstract
In recent years, we have been investigating the development of the ERIX (The Electrolytic Reduction and Ion Exchange) process for reprocessing spent FBR-MOX fuel. This process uses electrolytic reduction and ion exchange techniques to recover U, Pu from spent FBR-MOX fuel solution. It was found that despite of the high nitric acid concentration, U(VI) can be effectively reduced to U(IV) using a flow type electrolytic cell in the existence of hydrazine and the U(IV) can be completely separated from fission products by the anion exchanger, AR-01. In addition, it was proposed that a part of U is assigned to be recovered together with Pu and Np for reusing as a FBR-MOX fuel. For that purpose, we are investigating an efficient elution method of Pu(IV) and U(IV) from AR-01. In this work, to develop an efficient elution method of U(IV) from AR-01, we have examined the U(IV) elution behavior by formic acid and the complex-formation of U(IV) with HCOO-.
| Original language | English |
|---|---|
| Pages (from-to) | 400-402 |
| Number of pages | 3 |
| Journal | Journal of Alloys and Compounds |
| Volume | 451 |
| Issue number | 1-2 |
| DOIs | |
| Publication status | Published - 2008 Feb 28 |
| Externally published | Yes |
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Keywords
- FBR-MOX
- Formic acid
- Ion exchange
- Reprocessing
- Separation
- Spent nuclear fuel
- U(IV)
ASJC Scopus subject areas
- Metals and Alloys
Cite this
An efficient elution method of tetravalent uranium from anion exchanger by using formic acid solution. / Arai, Tsuyoshi; Wei, Yuezhou; Kumagai, Mikio.
In: Journal of Alloys and Compounds, Vol. 451, No. 1-2, 28.02.2008, p. 400-402.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - An efficient elution method of tetravalent uranium from anion exchanger by using formic acid solution
AU - Arai, Tsuyoshi
AU - Wei, Yuezhou
AU - Kumagai, Mikio
PY - 2008/2/28
Y1 - 2008/2/28
N2 - In recent years, we have been investigating the development of the ERIX (The Electrolytic Reduction and Ion Exchange) process for reprocessing spent FBR-MOX fuel. This process uses electrolytic reduction and ion exchange techniques to recover U, Pu from spent FBR-MOX fuel solution. It was found that despite of the high nitric acid concentration, U(VI) can be effectively reduced to U(IV) using a flow type electrolytic cell in the existence of hydrazine and the U(IV) can be completely separated from fission products by the anion exchanger, AR-01. In addition, it was proposed that a part of U is assigned to be recovered together with Pu and Np for reusing as a FBR-MOX fuel. For that purpose, we are investigating an efficient elution method of Pu(IV) and U(IV) from AR-01. In this work, to develop an efficient elution method of U(IV) from AR-01, we have examined the U(IV) elution behavior by formic acid and the complex-formation of U(IV) with HCOO-.
AB - In recent years, we have been investigating the development of the ERIX (The Electrolytic Reduction and Ion Exchange) process for reprocessing spent FBR-MOX fuel. This process uses electrolytic reduction and ion exchange techniques to recover U, Pu from spent FBR-MOX fuel solution. It was found that despite of the high nitric acid concentration, U(VI) can be effectively reduced to U(IV) using a flow type electrolytic cell in the existence of hydrazine and the U(IV) can be completely separated from fission products by the anion exchanger, AR-01. In addition, it was proposed that a part of U is assigned to be recovered together with Pu and Np for reusing as a FBR-MOX fuel. For that purpose, we are investigating an efficient elution method of Pu(IV) and U(IV) from AR-01. In this work, to develop an efficient elution method of U(IV) from AR-01, we have examined the U(IV) elution behavior by formic acid and the complex-formation of U(IV) with HCOO-.
KW - FBR-MOX
KW - Formic acid
KW - Ion exchange
KW - Reprocessing
KW - Separation
KW - Spent nuclear fuel
KW - U(IV)
UR - http://www.scopus.com/inward/record.url?scp=38349128434&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=38349128434&partnerID=8YFLogxK
U2 - 10.1016/j.jallcom.2007.04.156
DO - 10.1016/j.jallcom.2007.04.156
M3 - Article
AN - SCOPUS:38349128434
VL - 451
SP - 400
EP - 402
JO - Journal of Alloys and Compounds
JF - Journal of Alloys and Compounds
SN - 0925-8388
IS - 1-2
ER -