TY - GEN
T1 - Development of the ERIX process for reprocessing spent FBR-MOX fuel - Outline of the process and recent research results
AU - Wei, Yuezhou
AU - Arai, Tsuyoshi
AU - Kumagai, Mikio
AU - Bruggeman, Aime
PY - 2003/12/1
Y1 - 2003/12/1
N2 - To develop an advanced technology for reprocessing spent FBR-MOX fuel, we have proposed a new aqueous reprocessing system named ERIX Process (The Electrolytic Reduction and Ion Exchange Process). This process consists of (1) Pd removal by selective adsorption using a specific anion exchanger; (2) electrolytic reduction for the valence adjustment of the major actinides including U, Pu, Np and some fission products such as Tc and Ru; (3) anion exchange separation for the recovery of U, Pu and Np using a new type of anion exchanger, AR-01; and (4) selective separation of long-lived minor actinides (MA=Am, Cm) by extraction chromatography. In this work, a hot test using an irradiated MOX-fuel solution was carried out by the column packed with SiPyR-N3 anion exchanger to evaluate the removal behavior of Pd contained in spent fuel solution. Furthermore, recent experiment results on electrolytic reduction and anion exchange separation using simulated spent fuel solutions containing U and the platinum group FP elements such as Ru, Rh and Pd are also reported.
AB - To develop an advanced technology for reprocessing spent FBR-MOX fuel, we have proposed a new aqueous reprocessing system named ERIX Process (The Electrolytic Reduction and Ion Exchange Process). This process consists of (1) Pd removal by selective adsorption using a specific anion exchanger; (2) electrolytic reduction for the valence adjustment of the major actinides including U, Pu, Np and some fission products such as Tc and Ru; (3) anion exchange separation for the recovery of U, Pu and Np using a new type of anion exchanger, AR-01; and (4) selective separation of long-lived minor actinides (MA=Am, Cm) by extraction chromatography. In this work, a hot test using an irradiated MOX-fuel solution was carried out by the column packed with SiPyR-N3 anion exchanger to evaluate the removal behavior of Pd contained in spent fuel solution. Furthermore, recent experiment results on electrolytic reduction and anion exchange separation using simulated spent fuel solutions containing U and the platinum group FP elements such as Ru, Rh and Pd are also reported.
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UR - http://www.scopus.com/inward/citedby.url?scp=2642511597&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:2642511597
SN - 0894486772
T3 - Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy
SP - 479
EP - 484
BT - Global 2003
T2 - Global 2003: Atoms for Prosperity: Updating Eisenhower's Global Vision for Nuclear Energy
Y2 - 16 November 2003 through 20 November 2003
ER -