PCaPAC2012 - List of Authors (Das, M.K.)

Paper

Title

Page

An Embedded System Based Computer Controlled Process Automation for Recovery and Purification of ^99mTc from (n, γ)⁹⁹Mo

211

A. De, P. Bhaskar, A. Dutta Roy, M. Garai, V.K. Khare, S. Kumari, S.S. Pal, S. Saha, S.K. Thakur
VECC, Kolkata, India
L. Barua, S. Chattopadhyay, M.K. Das, U. Kumar, S. Saha Das
BRIT, Bidhan Nagar, India

⁹⁹Mo produced ^99mTc (t1/2=6hr, 140keV γ-ray) is the most useful radioisotope for nuclear diagnostics. High specific activity ⁹⁹Mo is supplied globally mainly by five old reactors whose routine or unscheduled maintenance shutdown causes supply irregularities that adversely affects patient management in nuclear medicine centres. ^99mTc may also be produced via ⁹⁸Mo(n,γ) in a natural MoO₃ target in reactor or by ¹⁰⁰Mo(n,2n)⁹⁹Mo or ¹⁰⁰Mo(p,2n)^99mTc reaction in cyclotron. To meet the crisis proposals are there to produce ⁹⁹Mo by ¹⁰⁰Mo(n,2n)⁹⁹Mo or ^99mTc directly by ¹⁰⁰Mo(p,2n)^99mTc in a cyclotron. Of the several separation methods of ^99mTc from molybdenum, the most common are adsorption column chromatography, sublimation and liquid-liquid solvent extraction. The conventional methods besides being cumbersome are often hazardous, polluting, require skilled manpower and facilities like fume hood and so are not always practically feasible for hospitals. To address these, VECC and BRIT, Kolkata have collaborated to develop an embedded system based automated ⁹⁹Mo/^99mTc generator from low specific activity ⁹⁹Mo using solvent extraction technique, supervised by a PC based GUI.

Poster THPD36 [0.428 MB]

Paper	Title	Page
THPD36	An Embedded System Based Computer Controlled Process Automation for Recovery and Purification of ^99mTc from (n, γ)⁹⁹Mo	211
	A. De, P. Bhaskar, A. Dutta Roy, M. Garai, V.K. Khare, S. Kumari, S.S. Pal, S. Saha, S.K. Thakur VECC, Kolkata, India L. Barua, S. Chattopadhyay, M.K. Das, U. Kumar, S. Saha Das BRIT, Bidhan Nagar, India
	⁹⁹Mo produced ^99mTc (t1/2=6hr, 140keV γ-ray) is the most useful radioisotope for nuclear diagnostics. High specific activity ⁹⁹Mo is supplied globally mainly by five old reactors whose routine or unscheduled maintenance shutdown causes supply irregularities that adversely affects patient management in nuclear medicine centres. ^99mTc may also be produced via ⁹⁸Mo(n,γ) in a natural MoO₃ target in reactor or by ¹⁰⁰Mo(n,2n)⁹⁹Mo or ¹⁰⁰Mo(p,2n)^99mTc reaction in cyclotron. To meet the crisis proposals are there to produce ⁹⁹Mo by ¹⁰⁰Mo(n,2n)⁹⁹Mo or ^99mTc directly by ¹⁰⁰Mo(p,2n)^99mTc in a cyclotron. Of the several separation methods of ^99mTc from molybdenum, the most common are adsorption column chromatography, sublimation and liquid-liquid solvent extraction. The conventional methods besides being cumbersome are often hazardous, polluting, require skilled manpower and facilities like fume hood and so are not always practically feasible for hospitals. To address these, VECC and BRIT, Kolkata have collaborated to develop an embedded system based automated ⁹⁹Mo/^99mTc generator from low specific activity ⁹⁹Mo using solvent extraction technique, supervised by a PC based GUI.
	Poster THPD36 [0.428 MB]