Production of radioisotopes in the BR2 high-flux reactor for applications in nuclear medicine and industry

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Abstract

The BR2 reactor, put into operation in 1963 and refurbished in 1995-1997, is a 100 MW High-Flux 'Materials Testing Reactor' which provides thermal neutron fluxes up to e+15 n/cm².s. The production of radioisotopes, characterized by high specific activities, are carried out in dedicated in-core devices within standard irradiation cycles of 3 to 4 weeks and in accordance with a 'Quality System' that has been certified to the requirements of the "EN ISO 9001 : 2000" in November 2003. Due to its operating flexibility, its reliability and its production capacity, the BR2 reactor is considered as a major facility for a routine supply of radioisotopes such as Mo-99 (Tc-99m), I-131, Xe-133, Ir-192, Re-186, Sm-153, Er-169, Y-90, P-32, W-188 (Re-188), Hg-203, Br-82, Kr-79, Ar-41, I-125, Lu-177, Sr-89, Co-60, Yb-169, Nd-147, ... It will continue to play this role with the possibility of an extra operating cycle in the near future and the realization of various 'test' irradiations to develop the production of new radioisotopes. Some irradiation devices allow the loading and unloading of irradiated targets during the operation of the reactor. Hot cells and storage facilities are available to prepare and organize the shipment of the irradiated targets to dedicated processing facilities.

Details

Original languageEnglish
Pages (from-to)333-337
JournalJournal of Labelled Compounds and Radiopharmaceuticals
Volume50
Issue number5-6
DOIs
Publication statusPublished - Apr 2007
Event9th International Symposium on the Synthesis and Applications of Isotopically Labelled Compounds - International Isotope Society (IIS), Edinburgh, United Kingdom
Duration: 16 Jul 200620 Jul 2006

Keywords

  • Radioisotopes, Production, BR2 High-Flux Reactor

ID: 327720