Recent Trends in Radioisotope Production by Using Cyclotron

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Presentation transcript:

Recent Trends in Radioisotope Production by Using Cyclotron Sujata Saha Das BRIT, VECC, Kolkata. TMUFC-2012

Radioisotope Use in Nuclear Medicine . Radioisotope Use in Nuclear Medicine Nuclear Medicine Application in Radioisotope (Organ Imaging) Diagnostic 99mTc 80% Other Radioisotopes 20% Therapeutic TMUFC-2012

Important Radioisotopes used in Diagnostic Imaging Half life, hour Decay mode 99mTc 6 IT 18F 1.83 b+ 201Tl 73.5 EC 123I 13.3 67Ga 78.3 TMUFC-2012

Speciality of 99mTc Nuclear Property: 140 keV -ray, 6 hr half life Exists in several oxidation states (+I to +VII) Ability to form Chelating complex TMUFC-2012

Fission of 235U Mo-99 at peak of fission mass distribution ~ 6 % of fissions yield Mo-99 (Half life of 66 h) TMUFC-2012

Fission based 99Mo production at research reactors worldwide Country Name Target type Share of Production % Canada NRU HEU 40 Netherlands HFR 30 Belgium BR-2 10-15 South Africa Safari-1 France Osiris 5-8 TMUFC-2012

Global Supply Chain of 99Mo and Subsequent Utilization Schematics TMUFC-2012

Radioisotope Generators Parent longer half life > Daughter shorter half life > 99Mo 66h, b- 99mTc 6h, IT 99Tc TMUFC-2012

Alternative Production Routes Neutron approaches –LEU 235U(n,F)99Mo –98Mo(n,γ)99Mo Photon approaches –238U(γ,F) 99Mo –100Mo(γ,n) 99Mo Proton approach –100Mo(p,2n)99mTc (Direct production ) 1971 – Beaver and Hupf report 100Mo(p,2n)99mTc in JNM Vol. 12 pp 739-741 TMUFC-2012

Isotopic Composition of Molybdenum Isotope Natural Enriched 97.39% Enriched 99.54% 92Mo 14.85 0.005 0.0060 94Mo 9.25 0.005 0.0051 95Mo 15.92 0.005 0.0076 96Mo 16.68 0.005 0.0012 97Mo 9.55 0.01 0.0016 98Mo 24.13 2.58 0.41 100Mo 9.63 97.39 99.54 TMUFC-2012

Reactions on Other Molybdenum Isotopes TMUFC-2012

Theoretical Calculations - Excitation Functions 100Mo(p,x) reactions of highest probability 99gTc 99gTc 98Tc 98Tc 99mTc 99mTc 99Mo 99Mo A. Celler, X. Hou, F. Bénard, T. Ruth, Phys. Med. Biol. 2011, 56, 5469 TMUFC-2012

Theoretical Calculations: Yield vs. Energy Natural (9.63%) 100Mo Enriched (99.54%) 100Mo TMUFC-2012

Our Findings on 99mTc Production by natMo(p,xn) Reactions: Part of IAEA CRP Work TMUFC-2012

Process Schematic Diagram (Patented Work) TMUFC-2012

Apparatus for Chemical Processing of 99mTc TMUFC-2012

extraction methodology (IAEA CRP work) Chemical Processing unit for separation of 99mTc from molybdenum using solvent extraction methodology (IAEA CRP work) TMUFC-2012

Challenges in 99mTc Production in Cyclotron Target Fabrication Electroplating (Electroplated is not thick enough for irradiation) Pressing and sintering Target Recovery Enriched targets (>97%) required are costly ($ 2-4 / mg) TMUFC-2012

List of Publications on 99mTc An automated computer controlled system for recovery of medically useful 99mTc from (n,g)99Mo produced in research reactor: a BRIT-VECC Collaboration (2010) VECC Newsletter, Vol. 12(3), pp.3-4, September. Chattopadhyay S., Saha Das S., Barua L. (2010) A simple and rapid technique for recovery of 99mTc from low specific activity (n,γ)99Mo based on solid-liquid extraction and column chromatography methodologies. Nucl. Med. Biol. 37 (1), 17-20. Chattopadhyay S., Saha Das S., Barua L. (2010) A simple and rapid technique for recovery of 99mTc from low specific activity (n,γ)99Mo based on solvent extraction and column chromatography . Appl. Radiat. Isot., 68(1), 1-4. Chattopadhyay S., Saha Das S., Das M. K., Goomer N. C. (2008) Recovery of 99mTc from Na2[99Mo]MoO4 solution obtained from reactor produced (n,γ)99Mo using a tiny Dowex-1 column in tandem with a small alumina column. Appl. Radiat. Isot., 66(12), 1814-1817. Chattopadhyay S. and Das M. K. (2008) A novel technique for the effective concentration of 99mTc from a large alumina column loaded with low specific-activity (n, γ)-produced 99Mo. Appl. Radiat. Isot., 66 (10), 1295-1299. Chattopadhyay S., Das M. K., Sarkar B. R. and Ramamoorthy N. (2002) Separation of pertechnetate from molybdate by anion-exchange chromatography : Recovery of 99mTc from (n, g)99Mo and suitability for use in central radiopharmacy (CRPh). Radiochimica Acta, 90(7), 417-421. Chattopadhyay S., Das M. K., Sarkar S. K., Saraswathy P. and Ramamoorthy N. (2002) A novel 99mTc delivery system using (n, g)99Mo adsorbed on a large alumina column in tandem with Dowex-1 and AgCl columns. Appl. Radiat. Isot. 57, 7-16. TMUFC-2012

TMUFC-2012

68Ge/68Ga Generator 68Ga is a Generator produced positron emitter This generator makes positron emitters available in a place far away from a cyclotron centre This generator can last for more than 1 Year 90 % of equilibrium activity is reaches in 4h 100mCi 68Ge costs Rs. 13.5 lakh TMUFC-2012

68Ge/68Ga Generator Nuclear reaction: 69Ga(p, 2n) 68Ge 68Ge 68Ga 68Zn smax = ~550mb at ~20 MeV Typical Production data Ep :~ 25MeV, Ip :~50mA, Duration of irradiation: 4 weeks 68Ge yield: 400-500 mCi at EOB 271d, EC 68m, b+ TMUFC-2012

Commercial Route of 68Ge Production 69Ga + p 68Ge + 2n Energy range for production15 - 30 MeV TMUFC-2012

68Ge/68Ga Generator Production of 68Ge Preparation of Generator 69Ga(p, 2n)68Ge Preparation of Generator 66Zn(a, 2n) 68Ge TMUFC-2012

Internal Target Target is mounted at the end of the Target probe shaft Cooling water Cu Base Electroplated Line Zinc Isometric view Longitutudinal section Cyclotron Dee Internal target Cooling water line TMUFC-2012

Evaluation of the Indigenously Made 68Ge/68Ga Generator TMUFC-2012

68Ge Breakthrough TMUFC-2012

65Zn Impurity TMUFC-2012

Acknowledgement All my colleagues in BRIT, VECC Mechanical Engineering Group Power Supplies & Instrumentation Division Nuclear Electronics Section Accelerator Physics Division RIB Group TMUFC-2012

Thank You TMUFC-2012