Ponente
Descripción
The International Fusion Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES) will be an experimental facility providing a high-energy and high-intensity neutron spectrum. Its primary purpose is to test materials under nuclear fusion irradiation conditions to qualify them for the future DEMO nuclear fusion power plant. Material specimens will be housed inside the High Flux Test Module (HFTM), located just behind the neutron source.
Beyond its primary functionality, IFMIF-DONES holds immense potential for additional socially and economically beneficial applications. One such application is the production of Molybdenum-99 (99Mo), a radioactive isotope critical for the generation of Technetium-99m (99mTc), the most widely used radiopharmaceutical for cancer diagnostics. Implementing this capability would not only address the current global shortages of 99Mo but also enhance the public perception of IFMIF-DONES as a multifaceted facility with significant societal contributions. This positive public image could, in turn, improve the facility's eligibility for state funding and support.
This work discusses the newly designed device, developed in collaboration with EAI, for producing radioisotopes. The device consists of a duct mechanism that laterally inserts molybdenum plates into the IFMIF-DONES Test Cell. The plates, enriched with 100Mo, are irradiated for six days before being mechanically extracted and replaced with new plates. This cyclical process ensures continuous production of 99Mo through the 100Mo(n,2n)99Mo reaction, which is not achievable in nuclear fission reactors.
This technological solution provided a reliable alternative for 99Mo production, offering a direct economic benefit through the supply of these radioisotopes. This dual advantage of societal and economic gains underscores the strategic value of incorporating radioisotope production into the IFMIF-DONES facility. However, ongoing efforts are focused on addressing the technological challenges to optimize the balance between safety requirements and maximizing radioisotope production