• DocumentCode
    1299123
  • Title

    Calculation and Evaluation of Fission Yields and Capture Cross Sections Leading to the Production of Therapeutic Radionuclide by Means of Nuclear Reactors

  • Author

    Sublet, Jean-Christophe

  • Author_Institution
    DEN, CEA, St. Paul lez Durance, France
  • Volume
    56
  • Issue
    4
  • fYear
    2009
  • Firstpage
    2397
  • Lastpage
    2409
  • Abstract
    Much progress has been made in nuclear medicine that involves the use of radionuclides for both diagnosis and therapy. Because of this qualitative and quantitative growth, the adoption of a set of established radionuclides for various applications, the methods of nuclide production need to be addressed and consideration given to other, emerging radionuclides that are judged to be developing in importance. The methods involved are characterized by the transmutation of isotopes by neutron-induced reactions and decays. Therefore, newly evaluated cross sections, fission yields and decay characteristics of relevance to the reactor production of those therapeutic radionuclides have been reviewed. Considerations of the decay schemes of all the nuclides involved are also included.
  • Keywords
    accelerator-based transmutation; patient diagnosis; radiation therapy; radioisotope imaging; capture cross sections; diagnosis; fission yields; isotopes transmutation; neutron-induced reactions; nuclear medicine; nuclear reactors; nuclide production; therapeutic radionuclide; Fission reactors; Inductors; Isotopes; Medical diagnostic imaging; Medical treatment; Neutrons; Nuclear medicine; Production; Strontium; Uncertainty; Nuclear medicine; radioisotope production; therapeutic radionuclide;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.2009.2023215
  • Filename
    5204588