Development of an electrochemical 90Sr-90Y generator for separation of 90Y suitable for targeted therapy

被引:94
作者
Chakravarty, Rubel [1 ]
Pandey, Usha [1 ]
Manolkar, Remani B. [1 ]
Dash, Ashutosh [1 ]
Venkatesh, Meera [1 ]
Pillai, M. R. Ambilcalmajan [2 ]
机构
[1] Bhabha Atom Res Ctr, Radiopharmaceut Div, Bombay 400085, Maharashtra, India
[2] IAEA, Div Phys & Chem Sci, Ind Applicat & Chem Sect, A-1400 Vienna, Austria
关键词
Sr-90-Y-90; generator; electrochemical separation; radionuclidic purity; Sr-90; contamination; targeted therapy; Kamadhenu; CARRIER-FREE Y-90; MICROSPHERE TREATMENT; RADIONUCLIDE THERAPY; MEDICAL APPLICATIONS; RADIOIMMUNOTHERAPY; RADIOISOTOPE; PURIFICATION; CHEMISTRY; LYMPHOMA; KSM-17;
D O I
10.1016/j.nucmedbio.2007.10.009
中图分类号
R8 [特种医学]; R445 [影像诊断学];
学科分类号
1002 ; 100207 ; 1009 ;
摘要
Y-90 of high specific activity and very high radionuclidic purity (>99.998%) is essential for targeted therapy Since the current methods used for the preparation of Y-90 from Sr-90 are not adaptable for use in a central/hospital radiopharmacy, a simple Sr-90-Y-90 generator system based on electrochemical separation technique was developed. Methods: Two-cycle electrolysis procedure was developed for separation of Y-90 from Sr-90 in nitrate solution. The first electrolysis was performed for 90 min in Sr-90(NO3)(2) feed solution at pH 2-3 at a potential of -2.5V with 100-200 mA current using platinum electrodes. The second electrolysis was performed for 45 min in 3 mM HNO3 at a potential of -2.5V with 100 mA current. In this step, the cathode from the first electrolysis containing Y-90 was used as anode along with a fresh circular platinum electrode as cathode. The Y-90 deposited on the circular cathode after the second electrolysis was dissolved in acetate buffer to obtain Y-90 acetate, suitable for radiolabeling. Results: >96% recovery of Y-90 could be achieved in each cycle, with an overall decay corrected yield of >90%. The recovered Y-90 had high radionuclidic purity with barely 30.2 +/- 15.2 kBq (817 +/- 411 nCi) of Sr-90 per 37 GBq (1 Ci) of Y-90 (0.817 +/- 0.411 ppm). Consistent and repeated separation could be demonstrated using up to 1.85 GBq (50 mCi) of Sr-90. The generator was named "Kamadhenu," the eternally milk-yielding Indian mythological cow. Conclusions: A technique suitable for adaptation at central radiopharmacies for obtaining therapeutic quantities of pure Y-90 has been developed. (c) 2008 Elsevier Inc. All rights reserved.
引用
收藏
页码:245 / 253
页数:9
相关论文
共 34 条
[1]   Separation of carrier-free 90Y from high level waste by extraction chromatographic technique using 2-ethylhexyl-2-ethylhexyl phosphonic acid (KSM-17) [J].
Achuthan, PV ;
Dhami, PS ;
Kannan, R ;
Gopalakrishnan, V ;
Ramanujam, A .
SEPARATION SCIENCE AND TECHNOLOGY, 2000, 35 (02) :261-270
[2]  
[Anonymous], 1959, NAT BUR STAND HDB, V69, P38
[3]  
Breeman WAP, 2007, ANTI-CANCER AGENT ME, V7, P345
[4]  
CHINOL M, 1987, J NUCL MED, V28, P1465
[5]   PREPARATION OF A SR-90 Y-90 GENERATOR USING ZIRCONIUM ANTIMONATE [J].
DASH, A ;
BHATTACHARYYA, PK .
APPLIED RADIATION AND ISOTOPES, 1994, 45 (04) :415-417
[6]   Radioimmunotherapy for B-cell lymphoma:: Y90 ibritumomab tiuxetan and I131 tositumomab [J].
Davies, A. J. .
ONCOGENE, 2007, 26 (25) :3614-3628
[7]   Studies on the development of a two stage SLM system for the separation of carrier-free 90Y using KSM-17 and CMPO as carriers [J].
Dhami, P. S. ;
Naik, P. W. ;
Dudwadkar, N. L. ;
Kannan, R. ;
Achuthan, P. V. ;
Moorthy, A. D. ;
Jambunathan, U. ;
Munshi, S. K. ;
Dey, P. K. ;
Pandey, Usha ;
Venkatesh, Meera .
SEPARATION SCIENCE AND TECHNOLOGY, 2007, 42 (05) :1107-1121
[8]  
DIETZ ML, 1992, APPL RADIAT ISOTOPES, V43, P1093
[9]  
Ferrari M, 2006, J NUCL MED, V47, P105
[10]  
FRIEDLANDER G, 1981, NUCL RADIOCHEMISTRY, P296