[en] Radioisotopes produced with a cyclotron and their corresponding radiopharmaceuticals have already been shown to be extremely valuable in basic medical research, disease diagnosis and radiotherapy treatment. There are more than 200 cyclotron facilities worldwide and the number is growing every year. A number of the Member States have acquired cyclotrons for the purpose of producing radioisotopes for nuclear medicine and a number of others have expressed an interest in acquiring such facilities. This report is concerned with the production of four radiotracers: Iodine-123, Iodine-124, Thallium-201 and Palladium-103. Iodine-123 is already widely used in SPECT studies, I-124 has shown great promise and can be used for PET studies as well as in radiotherapy. Tl-201 is widely used throughout the world as ²⁰¹Tl⁺ for measuring cardiac blood flow. It is a routine tool that is needed for the Nuclear Medicine communities and can be made available by those countries possessing a cyclotron facility with 30 MeV protons. Moreover, as preliminary results dealing with the labelling of chelated polypeptides with trivalent cationic Tl-201 are very promising; the nuclide can also be tried as a potential substitute for Indium tracers in SPECT diagnosis involving polypeptides. Palladium-103, an Auger electron emitter, has become an extremely important radionuclide for therapy. The Co-ordinated Research Programme (CRP) focuses on the optimisation and standardisation of solid phase cyclotron target technology for the production of I-123, I-124, Tl-201 and Pd-103. In particular, as originally proposed and further discussed and agreed upon during the 1st Research Co-ordination Meeting, the main technical goals of the CRP are described as follows: (i) to investigate the possibility of using electrodeposited tellurium and melted tellurium oxide as target material for the production of I-123 and I-124. For the oxide target, the following parameters and techniques will be explored: 1) methods of deposition of the oxide on the metal target plate, 2) the stability of the oxide layer during storage and irradiation, 3) the thermal characteristics of the oxide layer especially during irradiation, 4) methods of radioiodine recovery such as dry distillation, and 5) reprocessing of the targets. For the electrodeposited tellurium targets, the improvement of the existing deposition method and the presently used recovery process (wet chemistry) will be done. (ii) to prepare a target for the production of Thallium-201 which will withstand high beam currents in the range of 100 μA or more This will be accomplished through the transfer of the technology available on the electrodeposition of Thallium onto copper plates to produce a smooth, stable surface. The techniques will include the preparation of the targets before irradiation, extraction of the desired radioisotope, and the processing and recovery of the enriched materials after irradiation. Furthermore, a standard procedure for the preparation of trivalent Tl-201 (²⁰¹Tl⁺) suitable for polypeptide labelling can be developed. (iii) to prepare a target for the production of Pd-103 from Rhodium. This will be accomplished by transferring the existing technology for the electrodeposition of Rh onto metal plates. The chemical removal of Rh will also be investigated as an integral goal of the CRP. Attempts will be made to investigate the production and quality control methods for the preparation of sealed sources for the treatment of prostate cancer