Search PubMed⌕ Search

SEARCH · Search PubMed

Results for “Radionuclide Generators”

Search indexed PubMed citations on genomics, clinical trials, systematic reviews and public health. Explore titles, authors and supplied subject terms, then open the PubMed record.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 289 records · Page 16Linked to original sources

[A new biological irradiator for the laboratory].

The use of high doses (15-20 Gy) of X- or gamma-rays to irradiate blood-derived materials is a common practice by now. It is usual especially when materials must be transfused into non-immunocompetent patients. This is done to avoid the so-called GVH disease. Nowadays, for this purpose, units containing radioactive gamma-emitting sources with high activity and long half-life (usually 137Cs) are on the market. The characteristics of these "irradiators" allow their implementation in any laboratory with no need of structural shieldings. In spite of it, serious accidents (e.g., fire, fallings, etc.) which could imply hazards for the operating staff and even the general population, cannot be excluded. At the same time, the problem of long-term disposal of exhausted sources cannot be neglected. For these reasons, a new type of self-shielded irradiator was designed. It is equipped with an X-ray tube, operating at nearly 200-kV voltage, with 12-mA anodic current. The system is water- and oil-cooled and can work for a long time without thermal overloads. In this paper, the environmental and dosimetric measurements for beam characterization are reported. The system can produce beams with satisfactory characteristics for this specific problem. Moreover, its use may greatly reduce administrative radioprotection problems.

Blood↗

TESLA Accelerator Installation at Vinca. Production of radioisotopes for nuclear-medical applications.

The construction of the TESLA Accelerator Installation has been in progress under way at Vinca. It was designed so that the parameters of its main part-the VINCY Cyclotron enable, besides other applications, also the production of a number of radioisotopes which can be used in nuclear medicine. The production of a given radioisotope includes the choice of nuclear reaction (type, energy and beam current of accelerated particles, cross section, yield, etc), target (chemical form, isotopic composition, thermal stability), procedure of chemical treatment of the target after irradiation, procedure of labeling and quality control of the obtained radiopharmaceutical. In the paper these aspects are shown on the example of the production of radioisotope 123I.

Cyclotrons↗

Clinical aspects of local and regional tumor therapy with 188Re-RC-160.

Somatostatin-receptors have been found to be overexpressed in a variety of neuro-endocrine and epithelial cancers. While the introduction of a long-acting somatostatin-analogue, octreotide, exerted mainly anti-cancer activity in neuro-endocrine tumors, no convincing results have been demonstrated in other cancers. RC-160, another somatostatin-analogue has been selected because of its high receptor affinity and its anti-cancer activity. 188Re is a generator produced radionuclide with favourable gamma and beta-emission, allowing diagnostic and therapeutic application. The results of in vivo biodistribution and therapeutic outcome following systemic, intralesional and intracavitary application in animal studies employing 188Re-RC-160 are summarized. Safety considerations, dosimetry estimates and applicable indications are outlined. The clinical impacts of this radiopharmaceutical in cancer management are discussed.

Animals↗

Results of regular study on radionuclidic purity of 99mTc obtained from 99Mo--99mTc generators.

A total of 39 99mTc eluates obtained from 9 99Mo--99mTc generators delivered by The Radiochemical Centre Amersham during one year was studied with regard to their radionuclide purity. Using a Ge(Li) spectrometer the contaminants 60Co, 103Ru, 131I, 134Cs, 140Ba, 140La and 188Re were found in 99mTc-eluates with average levels ranging from 2.9 X 10(-3) to 2.8 X 10(-1) per cent of 99mTc activity. The additional total body absorbed dose caused by these contaminants, as calculated from their average content in 99mTc eluates, was less than 1% of the dose due to 99mTc pertechnetate.

Radiation Dosage↗