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Irradiation Technologies and Radioisotopes
Objectives:
- To develop production of new radioisotopes for industrial and medical use, to fulfill the demands of the national market;
- To ensure and develop the Institute technical and scientific potential in the radioisotope production field;
- To increase the utilization factor of the TRIGA-14MW reactor and its economical efficiency.
Research perspectives:
- Development of the radioisotopes production techniques aiming to obtain new radioisotopes: 99Mo from fission and 125I from irradiation of gases Xe;
- Development of new technologies for operation with new sealed irradiation sources;
- Development of new technologies to obtain targets for radioisotopes productions;
- Development and authorization of methods, measure and control chains for radioactive sources characteristic parameters.
Main results of research:
- Increase of the irradiation capacity through new irradiation devices;
- Development of a new computing method for the gamma flux and heating, in the raw material and structural materials of the irradiation devices inserted into the reactor core, necessary for the irradiation experiments design;
- Building of an integrated computes codes of neutronic computation able to cover the design area of the irradiation experiments for isotope production;
- Completion of a fabrication line for the metallic Iridium targets (sintered and nickel-plated, necessary to obtain sealed sources for industrial gamma radiography;
- Completion of a fabrication line for the metallic Cobalt targets (sintered and nickel-plated, necessary to obtain sealed sources with medical and industrial utilization;
- Manufacturing and supply of sealed sources for industrial gamma radiography, with the following characteristics:
- SR-Ir-A, whit max activity of 4,440 TBq (120 Ci) and focal spot of 3x3 mm;
- SR-Ir-B, whit max activity of 2,310 TBq ( 70 Ci) and focal spot of 2,5x2,5 mm;
- SR-Ir-C, whit max activity of 1,155 TBq (35 Ci) and focal spot of 2x2 mm;
- SR-Ir-D, whit max activity of 0,555 TBq (15 Ci) and focal spot of 1,5x1,5 mm;
- SR-Ir-E, whit max activity of 0,185 TBq (5 Ci) and focal spot of 1x1 mm;
- SR-Ir-F, whit max activity of 0,037 TBq (1 Ci) and focal spot of 0,5x0,5 mm.
Contact: CS II Petre BUSUIOC;
e-mail: petre.busuioc@nuclear.ro
Last update: 22.04.2010 |
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Nuclear 2010
The Third Annual International Conference on Sustainable Development through Nuclear Research and Education
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