• Title/Summary/Keyword: Radioisotope production

Search Result 84, Processing Time 0.024 seconds

The Effect of Process Parameters on Sealing Quality for Ir-192 Radiation Source Capsule using Resistance Spot Welding (Ir-192 방사선원의 밀봉 용접부 품질에 미치는 저항용접 공정변수의 영향)

  • Han, In-Su;Son, Kwang-Jae;Lee, Young-Ho;Lee, You-Hwang;Lee, Jun-Sig;Jang, Kyung-Duk;Park, Ul-Jae;Park, Chun-Deuk
    • Journal of Welding and Joining
    • /
    • v.27 no.1
    • /
    • pp.65-70
    • /
    • 2009
  • Ir-192 radiation sealed sources are widely employed to the therapeutic applications as well as the non-destructive testing. Production of Ir-192 sources requires a delicate but robust welding technique because it is employed in a high radioactive working environment. A GTA(Gas Tungsten Arc) welding technique is currently well established for this purpose. However, this welding method requires a frequent replacement of the electrode, which results in the delay of the production to take a preparatory action such as to isolate the radiation sources from the working place before getting access to the welding machine. Hence, a resistance welding technique is considered as an alternative method of the GTA welding technique. The advantages of resistance welding are high welding speed and high-rate production. Also it has very long life of electrode comparing to GTA welding. In this study, the resistance welding system and proper welding conditions were established for sealing Ir-192 source capsule. As a results of various experiments, it showed that electrode displacement can be employed as a indicator to predict welding quality. We proposed two mathematical models(linear and curvilinear) to estimate electrode displacement with process parameters such as applied force, welding current and welding time by using regression analysis method. Predicting results of both linear and curvilinear model were relatively good agreement with experiment.

Development of resistance welding technology for producing Ir-192 industrial radiation sources (Ir-192 산업용 방사선원의 생산을 위한 저항용접기술 개발)

  • Han, In-Su;Son, Kwang-Jae;Lee, Jun-Sig;Jang, Kyung-Duk;Park, Ul-Jae
    • Proceedings of the KWS Conference
    • /
    • 2007.11a
    • /
    • pp.288-290
    • /
    • 2007
  • Ir-192 source is one of the most widely used radioisotopes in the field of non-destructive testing applications. To obtain radiation safety it is necessary to take into consideration integrity of welded joint in the production of sealed radiation source. Generally, the quality of a resistance welded joint is strongly influenced by process parameters during the welding process such as current, welding time and applied force. In this study, resistance welding technology and system were developed for sealing of Ir-192 industrial radiation source capsules. In order to evaluate the weld quality in real time, quantitative relationships between process parameters and electrode displacement were also established.

  • PDF

Therapeutic radionuclides (치료용 방사성동위원소)

  • Choi, Sun-Ju;Hong, Young-Don;Lee, So-Young
    • Nuclear Medicine and Molecular Imaging
    • /
    • v.40 no.2
    • /
    • pp.58-65
    • /
    • 2006
  • Since the development of sophisticated molecular carriers such as octereotides for peptide receptor targeting and monoclonal antibodies against various antigens associated with specific tumor types, radionuclide therapy (RNT) employing open sources of therapeutic agents is promising modality for treatment of tumors. furthermore, the emerging of new therapeutic regimes and new approaches for tumor treatment using radionuclide are anticipated in near future. In targeted radiotherapy using peptides and other receptor based tarrier molecules, the use of radionuclide with high specific activity in formulating the radiopharmaceutical is essential in order to deliver sufficient number of radionuclides to the target site without saturating the target. In order to develop effective radiopharmaceuticals for therapeutic applications, it is crucial to carefully consider the choice of appropriate radionuclides as well as the tarrier moiety with suitable pharmacokinetic properties that could result in good in vivo localization and desired excretion. Up to date, only a limited number of radionuclides have been applied in radiopharmaceutical development due to the constraints in compliance with their physical half-life, decay characteristics, cost and availability in therapeutic applications. In this review article, we intend to provide with the improved understanding of the factors of importance of appropriate radionuclide for therapy with respect to their physical properties and therapeutic applications.

Calculation of Proton-Induced Reactions on Tellurium Isotopes Below 60 MeV for Medical Radioisotope Production

  • Kim, Doohwan;Jonghwa Chang;Yinlu Han
    • Nuclear Engineering and Technology
    • /
    • v.32 no.4
    • /
    • pp.361-371
    • /
    • 2000
  • The 123Te(p,n)123I, 124Te(p,n)124I and 124Te(p,2n)123I reactions, among the many reaction channels opened, are the major reactions under consideration from a diagnostic purpose because reaction residuals as the gamma emitters are used for most radiophamaceutical applications involving radioiodine. Based on the available experimental data, the absorption cross sections and elastic scattering angular distributions of the proton-induced nuclear reaction on Te isotopes below 60 MeV are calculated using the optical model code APMNK. The transmission coefficients of neutron, proton, deuteron, trition and alpha particles are calculated by CUNF code and are fed into the GNASH code. By adjusting level density parameters and the pair correction values of some reaction channels, as well as the composite nucleus state density constants of the pre-equilibrium model, the production cross sections and energy-angle correlated spectra of the secondary light particles, as well as production cross sections and energy distributions of heavy recoils and gamma rays are calculated by the statistical plus pre-equilibrium model code GNASH. The calculated results are analysed and compared with the experimental data taken from the EXFOR. The optimized global optical model parameters give overall agreement with the experimental data over both the entire energy range and all tellurium isotopes.

  • PDF

Production of Re-188 (Rhenium-188 생산)

  • Yang, Seung-Dae;Suh, Yong-Sup;Kim, Sang-Uk;Lim, Sang-Moo
    • 대한핵의학회:학술대회논문집
    • /
    • 1999.05a
    • /
    • pp.189-192
    • /
    • 1999
  • $^{188}Re$ (${\beta}^-=2.2$ MeV; ${\gamma}^-$=155 keV; $T_{1/2}$=16.9 hours) is an attractive therapeutic radioisotope which is produced from decay of reactor-produced tungsten-188 parent ($T_{1/2}$=69 days). $^{188}W$ has been produced from the double neutron capture reaction of $^{186}W.\;^{188}Re$ can be easily obtained by elution of saline on alumina based $^{188}W/^{188}Re$ generator, which is commercially available. Complexes labelled with $^{188}Re$ have been developed for the radiotherapy treatment of diseases because of the desirable nuclear properties of the radioisotope and it's chemical properties similar to those of technetium, a well established diagnostic agent.

  • PDF