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
Link To Document