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Country report: Pakistan. Second Research Co-ordination Meeting on Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, 22-26 March 2010, Vienna

Abstract

Various experiments were carried out for the separation of {sup 90}Y from {sup 90}Sr using colloid formation behavior of {sup 90}Y in basic pH range. When the acidic solution of {sup 90}Sr/{sup 90}Y was treated with NaOH and passed through a small glass wool column, more than 95% {sup 90}Y was retained on glass wool, which was further washed with 0.1 M NaOH. The {sup 90}Y was extracted in 1 M HCl. Radionuclidic purity was determined by half life measurement. The contamination of parent was less than 0.0001%. Similarly when the colloid was passed through membrane filter more than 95% {sup 90}Y was retained which was recovered by 1 M HCl. The contamination of {sup 90}Sr was less than 0.0001%. The stock solution of {sup 90}Sr/{sup 90}Y in NH{sub 4}OH/NaOH was again passed through Millipore filter paper or glass wool after one week. The retention of 90Y was insignificant. The equilibrium mixture of {sup 90}Sr/{sup 90}Y was acidified with HCl and again precipitated with addition of NH{sub 4}OH or NaOH. The basic solution was passed through the Millipore filter or glass wool. More than 90% activity of {sup 90}Y was retained, which was finally extracted in 1 M HCl It  More>>
Authors:
Mansur, M. S.; Mushtaq, A. [1] 
  1. Isotope Production Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad (Pakistan)
Publication Date:
Jul 01, 2010
Product Type:
Conference
Report Number:
IAEA-RC-1088.2
Resource Relation:
Conference: 2. Research Coordination Meeting on The Development of Therapeutic Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, Vienna (Austria), 22-26 Mar 2010; Related Information: In: Report on the 2{sup nd} Research Coordination Meeting on The Development of Therapeutic Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide. Working Document| 185 p.
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 62 RADIOLOGY AND NUCLEAR MEDICINE; ADSORPTION; AMMONIUM HYDROXIDES; COLLOIDS; CONTAMINATION; EFFICIENCY; GLASS; HYDROCHLORIC ACID; IMPURITIES; LABELLING; PAKISTAN; RADIOPHARMACEUTICALS; RADIOTHERAPY; RHENIUM 188; SODIUM HYDROXIDES; SOLUTIONS; STRONTIUM 90; YTTRIUM 90
OSTI ID:
22270096
Research Organizations:
International Atomic Energy Agency, Division of Physical and Chemical Sciences, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA14M3064091328
Availability:
Available from INIS in electronic form. Also available on-line: http://www-naweb.iaea.org/napc/iachem/meetings/RCMs/RC-1088-2_report_complete.pdf
Submitting Site:
INIS
Size:
page(s) 95-96
Announcement Date:
Oct 22, 2014

Citation Formats

Mansur, M. S., and Mushtaq, A. Country report: Pakistan. Second Research Co-ordination Meeting on Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, 22-26 March 2010, Vienna. IAEA: N. p., 2010. Web.
Mansur, M. S., & Mushtaq, A. Country report: Pakistan. Second Research Co-ordination Meeting on Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, 22-26 March 2010, Vienna. IAEA.
Mansur, M. S., and Mushtaq, A. 2010. "Country report: Pakistan. Second Research Co-ordination Meeting on Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, 22-26 March 2010, Vienna." IAEA.
@misc{etde_22270096,
title = {Country report: Pakistan. Second Research Co-ordination Meeting on Development of Radiopharmaceuticals Based on {sup 188}Re and {sup 90}Y for Radionuclide Therapy, 22-26 March 2010, Vienna}
author = {Mansur, M. S., and Mushtaq, A.}
abstractNote = {Various experiments were carried out for the separation of {sup 90}Y from {sup 90}Sr using colloid formation behavior of {sup 90}Y in basic pH range. When the acidic solution of {sup 90}Sr/{sup 90}Y was treated with NaOH and passed through a small glass wool column, more than 95% {sup 90}Y was retained on glass wool, which was further washed with 0.1 M NaOH. The {sup 90}Y was extracted in 1 M HCl. Radionuclidic purity was determined by half life measurement. The contamination of parent was less than 0.0001%. Similarly when the colloid was passed through membrane filter more than 95% {sup 90}Y was retained which was recovered by 1 M HCl. The contamination of {sup 90}Sr was less than 0.0001%. The stock solution of {sup 90}Sr/{sup 90}Y in NH{sub 4}OH/NaOH was again passed through Millipore filter paper or glass wool after one week. The retention of 90Y was insignificant. The equilibrium mixture of {sup 90}Sr/{sup 90}Y was acidified with HCl and again precipitated with addition of NH{sub 4}OH or NaOH. The basic solution was passed through the Millipore filter or glass wool. More than 90% activity of {sup 90}Y was retained, which was finally extracted in 1 M HCl It was concluded that for recovery of {sup 90}Y from {sup 90}Sr by colloid formation, the acidic solution of {sup 90}Sr/{sup 90}Y shall be freshly precipitated by NH{sub 4}OH or NaOH. It was also observed that the adsorption of {sup 90}Y was quite high when the {sup 90}Sr solution was left in a glass vial for the growth of {sup 90}Y. However it can be easily extracted after keeping it in boiling water bath for few minutes. The separated {sup 90}Y via colloid formation was used for the labeling of EDTMP. Labeling efficiency of {sup 90}Y-EDTMP was more than 98%.}
place = {IAEA}
year = {2010}
month = {Jul}
}