Production of pharmaceutical grade [Tl]Thallous chloride using 30 MeV cyclotron.

Multiple patient doses of [Tl]TlCl has been produced using electrodeposited enriched Tl in 30 MeV cyclotron (Cyclone-30) with 28 MeV proton energy at 50 μA beam current for 8 h. Ion Exchange Column Chromatography (IECC) and liquid-liquid extraction has been employed for semi-automated radiochemical separation and purification of produced [Tl]TlCl. The produced [Tl]TlCl was used in coronary artery disease (CAD) patients.

Preparation of [Ga]Ga-Chloride from Zn solid target for the synthesis of pharmaceutical grade [Ga]Ga-PSMA-11 and [Ga]Ga-DOTA-TATE.

Ga is produced from enriched zinc-68 target electrodeposited on copper base material which was irradiated with 15 MeV proton energy in 30 MeV cyclotron. A modified semi-automated separation and purification module was used to obtain pharmaceutical grade [Ga]GaCl in 35 ± 5 min. The quality of [Ga]GaCl produced was in accordance with Pharmeuropa 30.

Clinical doses production of pharmaceutical grade Sodium[F]Fluoride using modified integrated fluidic processor in a SYNTHERA® module.

A fully automated large-scale production of sodium [F]fluoride ([F]NaF) using SYNTHERA module with a modification in integrated fluidic processor (IFP) is reported. This modified IFP module is used to prepare [F]NaF with more than 98% non-decay corrected radiochemical yield (RCY) within 5 min with specifications in accordance with United State Pharmacopeia (USP) monograph. The graphical user interface (GUI) is designed to perform the synthesis steps either manually or automatically and give information to the operator during the course of production.

Clinical Efficacy of Sodium [99mTc] Pertechnetate from Low Specific Activity 99Mo/99mTc Autosolex Generator in Hospital Radiopharmacy Centre.

Background: Few nuclear reactors in the world producing high specific activity (HSA) 99Mo using enriched 235U (HEU), are aging and are planned for shut down in the near future. Further, HEU will not be freely available, due to safeguards, and the technology for 99Mo from low-enriched 235U (LEU) is not yet widely accepted since 239Pu contamination in the product is an issue. Production of 99mTc from low specific activity (LSA) 99Mo obtained from 98Mo(n,)99Mo reaction in research reactor and 100Mo(,n)99Mo reaction in accelerator or directly from 100Mo(p,2n)99mTc nuclear reaction in cyclotron, has been explored [1].

A compact solvent extraction based Mo/Tc generator for hospital radiopharmacy.

A compact and portable Mo-Tc generator based on solvent-extraction, mimic to the conventional Mo-Tc alumina column generator is much-needed commodity for use in hospital radiopharmacy setup. The present study includes the development of a portable, simple and low cost Mo/Tc-generator based on MEK solvent extraction technique to obtain a very high concentration of no-carrier added (nca) Tc solution, where low specific activity Mo source is obtained through Mo(n, γ)Mo reaction in a research reactor. The unit is intended for operation under the conditions of medical radiological laboratories.

Radioactive ion beams of In using ECR plasma sputtering method.

Radioactive ion beams of In (indium-111, half-life 2.8 days) have been produced using the plasma sputtering method in an electron cyclotron resonance (ECR) ion source at the Variable Energy Cyclotron Centre RIB facility. Indium isotopes were first produced by bombarding a natural silver target with a 32 MeV, 40 μA alpha particle beam from the K-130 cyclotron.

A simple method for preparation of pure Ga-acetate precursor for formulation of radiopharmaceuticals: Physicochemical characteristics of the Ga eluate of the SnO based- Ge/ Ga column generator.

Gallium-68 radioisotope is an excellent source in clinical positron emission tomography application due to its ease of availability from germanium-68 ( Ge)/gallium-68 ( Ga) generator having a shelf life of 1 year. In this paper, a modified method for purification of the primary eluate of Ge- Ga generator by using a small cation exchange resin (Dowex-50) column has been described. The breakthrough of Ge before and after purification of Ga eluate was 0.

Development of a Ne gas target for (22)Na production by proton irradiation.

The article presents the design and development of a neon gas target for the production of (22)Na using a proton beam from the room temperature cyclotron in Variable Energy Cyclotron Centre, Kolkata. The target design is made to handle a beam power of 85 W (17 MeV, 5 μA). The design is based on simulation using the computer code FLUKA for the beam dump and CFD-CFX for target cooling.

Preparation and evaluation of SnO2-based 68Ge/68Ga generator made from 68Ge produced through (nat)Zn(α,xn) reaction.

(68)Ge was produced by (nat)Zn(α,xn)(68)Ge reaction and its production yield was 31.82 kBq/μAh (0.86 μCi/μAh) at the end of irradiation (EOI).

A computerized compact module for separation of (99m)Tc-radionuclide from molybdenum.

An automated closed cycle module for the separation and recovery of various isotopes, radioactive or non-radioactive, using solvent extraction and column chromatography techniques, and in particular, for separation and recovery of (99m)Tc from low-medium specific activity (99)Mo, is described. The module may also be applicable for separation of (99m)Tc produced in a cyclotron. The module is safe and reliable to avoid human interference and hazards posed by handling of radioactive and hazardous chemicals.

Production of 61Cu using natural cobalt target and its separation using ascorbic acid and common anion exchange resin.

(61)Cu was produced by (nat)Co(α, xn)(61)Cu reaction. (61)Cu production yield was 89.5 MBq/μAh (2.

A simple and rapid technique for recovery of 99mTc from low specific activity (n,gamma)99Mo based on solid-liquid extraction and column chromatography methodologies.

A simple and inexpensive method has been developed for the separation of (99m)Tc from (99)Mo produced from the neutron activation of (98)Mo by (98)Mo(n,gamma)(99)Mo nuclear reaction. The recovery of (99m)Tc was performed by solid-liquid extraction based on alumina column chromatography. The overall radiochemical yield for the complete separation of (99m)Tc was 85-97% (n=5).

A simple and rapid technique for recovery of (99m)Tc from low specific activity (n,gamma)(99)Mo based on solvent extraction and column chromatography.

A simple and inexpensive method of separation of (99m)Tc from (99)Mo produced by neutron activation of (98)Mo via the (98)Mo(n,gamma)(99)Mo nuclear reaction is described. The recovery of (99m)Tc was performed by solvent extraction technique followed by column (active alumina) chromatography. The overall radiochemical yield for the complete separation of (99m)Tc was 85-95% (n=10).