Author: Peleshko, V.N.
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TUPSA33
Radioisotope Centre of Nuclear Medicine  
 
  • A.A. Khasin, R.G. Tertychnyy
    CDNM Ltd, Protvino, Russia
  • V.N. Peleshko, A.P. Soldatov
    IHEP, Moscow Region, Russia
 
  Funding: Work supported by the Ministry of Education and Science of the Russian Federation, the agreement ID 0000000007417-3I0002
The Centre for Development of nuclear medicine (CDNM Ltd) in partnership with the Institute of High Energy Physics of the National Research Centre Kurchatov institute (IHEP) is establishing in Protvino a manufacturing facility on the basis of 70 MeV proton cyclotron. The facility will be focused on production of medical isotopes including Sr-82, Ge-68, Cu-67, and others. Sr-82 and Ge-68 isotopes are of the high demand for production of Sr-82/ Rb 82 and Ge-68/Ga-68 radionuclide generators used in PET (Positron Emission Tomography) diagnostics of cardiac and oncological diseases respectively. Cardiac PET is a superior proven technology, which enables physicians to deliver a diagnosis with less artifactual defects and false-positive results. Wider spread of cardiac PET diagnostics is currently restrained by a shortage of Sr-82 isotope being produced by a limited number of manufacturers worldwide. Establishment of a Russian production site will make it possible to introduce very effective Rb-82- based cardiac PET diagnostics into clinical practices in Russia. CDNM's production facility will run a proton cyclotron Cyclone-70 manufactured by IBA (Ion Beam Applications), Belgium with target devices being developed in partnership with IHEP. CDNM's manufacturing facility will also have a radiochemistry lab for extraction and purification of radionuclide products and quality control laboratory.
 
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TUPSA49 Installation for Irradiation of Thin Foils by Halo Proton Beam on IHEP Accelerator 249
 
  • Ja.N. Rascvetalov, G.I. Krupny, M.A. Maslov, V.N. Peleshko
    IHEP, Moscow Region, Russia
 
  The halo of proton beam arises due to proton elastic and coulomb scattering on the internal target. On 70 GeV IHEP accelerator (U-70) halo contains up to several per-cent of proton beam. It was shown by Monte Carlo method that on thin target (0.05-1 g/cm2 foils) each halo proton crosses the foil specimen up to 103 - 105 times before it will be lost during U-70 cycle. The radiation damage level in foil specimens at 1020 crossings was estimated at about 0,17 dpa (displacement per atom). Accumulation of hydrogen and helium atoms during exposure was calculated for iron, nickel and chromium specimens. Some factors limiting the rate of accumulation of radiation damage and ways for its solutions are discussed. Simple installation with various material foils as targets is described together with the first proton expo-sure results of copper and aluminum foils. It is important, that foils irradiation by beam halo may be provided independently out of the main U-70 physical program. As concluded, radiation damage level compared with results got during one year research nuclear reactors can be accumulated during one U-70 run (one month).  
DOI • reference for this paper ※ https://doi.org/10.18429/JACoW-RUPAC2018-TUPSA49  
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WEPSB54 Selection of Materials for Target Station Equipment at Cyclotron Cyclon-70 391
 
  • E.N. Savitskaya, M.A. Maslov, S.A. Nikitin, V.N. Peleshko, N.V. Skvorodnev
    IHEP, Moscow Region, Russia
 
  Funding: Work supported by the Ministry of Education and Science of the Russian Federation, the agreement ID 0000000007417-3I0002
A Radioisotope Centre of Nuclear Medicine for commercial production of radioisotopes is under construction now in Protvino. It is based on IBA (Belgium) Cyclone 70 proton cyclotron with proton energy up to 70 MeV and beam current up to 750 uA. The proton beam is split into two halves to provide simultaneous operation of two target stations. NRC KI - IHEP develops the design of the target station to produce nuclides Sr82 and Ge68 by the 70 MeV proton beam with current up to 375uA (2.3x1015 proton/s). The present work is devoted to selection of target station materials to minimize the induced radioactivity of equipment during isotopes production. The main source of this radioactivity is a flux of secondary neutrons cre-ated from proton-nuclear interactions with target materials. The nucleon-nucleus interactions and the transport of particles in substances were simulated by package of Monte Carlo codes HADR99 and FAN15 specially adapted for this task. Time dependence of the activity of nuclides accumulated in surrounding equipment and the effective dose rate after the end of bombardment (EOB) were calculated. Several alloys were considered and aluminum alloy AMg2 was chosen as most promising base material.
 
DOI • reference for this paper ※ https://doi.org/10.18429/JACoW-RUPAC2018-WEPSB54  
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WEPSB55
On the Formation of Induced Radioactivity on the U-70 Proton Accelerator  
 
  • Ja.N. Rascvetalov, G.I. Britvich, G.I. Krupny, M.A. Maslov, V.N. Peleshko, E.N. Savitskaya
    IHEP, Moscow Region, Russia
 
  Global induced radioactivity levels on the main ring of proton 70 GeV accelerator (U-70) were estimated. Modeling results of induced radioactivity accumulation on the typical particle canal downstream internal target by Monte Carlo method are given. The wide set of various material specimens was espoused during one U-70 run in vicinity of internal target and specific radioactivity of identified long-lived nuclides was measured. Decay curves of ambient dose and specific radioactivity were calculated and analyzed for all activated specimens. Some fragments of U-70 equipment from radioactive waste storage also were investigated and specific radioactivity of their long-lived nuclides were measured. Unexpectedly 44Ti with 60 years half-life was identified in some cooper and stainless steel fragments. Production cross sections of 44Ti (and other nuclides) on copper were evaluated after irradiation by 50 GeV protons. These data can be used to provide radiation safety when working with radioactive elements of accelerator equipment, as well as storing and disposing of radioactive waste.  
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