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 :
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