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RadChem 2014
11–16 May 2014
Casino Conference Centre
Europe/Prague timezone
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Session
Production and Application of Radionuclides 2
PAR-2
16 May 2014, 08:30
Casino Conference Centre
Casino Conference Centre
Reitenbergerova 4/95, Mariánské Lázně, Czech Republic <font color=white>
Conveners
Production and Application of Radionuclides 2
Jiří Mizera
(
Nuclear Physics Institute, Academy of Sciences of the Czech Republic
)
Sung-Hee Jung
(
Korea Atomic Energy Research Institute
)
Presentation materials
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Contribution list
Timetable
171.
Generation and isolation of the positron emitter titanium-45
Mr
Tobias Wels
(
Forschungszentrum Jülich
)
16/05/2014, 08:30
Production and Application of Radionuclides
Verbal
Objectives: A very promising but so far rather less regarded non-standard PET-nuclide is titanium-45. Its low maximum positron energy in combination with the very weak γ-rays and its relatively long half-life of 184.8 min makes it especially suitable for investigations of slow (patho-)physiological processes. The radionuclide is accessible in high yields via the Sc-45(p,n)Ti-45 reaction and...
99.
Investigation of the possibility of production and purification of the therapeutic radionuclide 195mPt by bombarding the 193Ir target with neutrons
Dr
Nikolay Aksenov
(
Joint Institute for Nuclear Research
)
16/05/2014, 08:45
Production and Application of Radionuclides
Verbal
The advantage of using the Auger electron emitter 195mPt (T1/2 4.02 days) in medical radiotherapeutic applications are two-food. First there is high yield of low energy beta/gamma radiation, where each decay leads to more than 30 secondary electrons. Second, there is no radioactive contamination after the decay. Effective ways for optimization of the Pt isomer yield at low impurity content...
269.
Generators of alpha-emitting radionuclides 225Ac→221Fr→213Bi and 223Ra→219Rn→211Pb
Dr
Stanislav ERMOLAEV
(
Institute for Nuclear Research of Russian Academy of Sciences
)
16/05/2014, 09:00
Production and Application of Radionuclides
Verbal
Generators of alpha-emitting radionuclides are of great interest for targeted therapy of cancer. Among possible generator pairs, 225Ac/213Bi and 223Ra/211Pb are the most promising. In addition to α-particle’s properties attractive for nuclear medicine such as short range (50-100 μm) and high linear energy transfer (up to 100 keV/μm) in biological tissue, the mother radionuclides 225Ac and...
163.
Production of High Specific Activity Radiolanthanides for Medical Purposes using the Szilard-Chalmers method
Ms
Leila Safavi-Tehrani
(
University of California Irvine
)
16/05/2014, 09:15
Production and Application of Radionuclides
Verbal
Radioactive lanthanides have become an important imaging, diagnostic and therapeutic tool in the medical field. For example, the neutron rich samarium isotope of 153Sm has been proven to have desirable characteristics for treatment of bone cancer. However, for medical purposes, the radioactive lanthanide isotope must be produced at high specific activity, i.e. low concentration of inactive...
69.
Development of new sorbent materials for the preparation of 99Mo/99mTc generators
Vallín García Cruz
(
Delft University of Technology
)
16/05/2014, 09:30
Production and Application of Radionuclides
Verbal
99mTc is one of the most often applied radioisotopes in diagnostic imaging. 99mTc is typically supplied to hospitals in the form of a 99Mo/99mTc generator in order to facilitate regular availability. The 99Mo used to produce these generators is a fission product of 235U, and therefore it can only be obtained from just a few nuclear reactors in the world. The goal of this work is to investigate...
195.
Cyclotron production of Tc-99m - radionuclidic impurities profile and compatibility with commercial kits
Dr
Ondřej Lebeda
(
Nuclear Physics Institute AS CR, v.v.i., Řež, Czech Republic
)
16/05/2014, 09:45
Production and Application of Radionuclides
Verbal
Cyclotron production of Tc-99m via Mo-100(p,2n) reaction seems to be viable alternative to Mo-99/Tc-99m generators. It is already known that 1) one cyclotron is able to cover daily consumption of large metropolitan area (up to 1.7 GBq at EOB), 2) target processing and separation of Tc-99m as pertechnetate is more or less solved problem including recycling of Mo-100, 3) enough high enrichment...
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