1. The use of radionuclides offers possibilities for medical analysis and treatment: for diagnosing cancers by means of scintigraphy and tomography, allowing in-depth examinations of organs in operation, or for the treatment of tumours using radiotherapy, which uses radiation from radionuclides to destroy cancer cells (see chapter 5). Nuclear research or industrial facilities differ from the Basic Nuclear Installations (BNIs) involved directly in the generation of electricity (nuclear power reactors and “fuel cycle” facilities) or waste management. Traditionally, most of these BNIs are operated by the Alternative Energies and Atomic Energy Commission (CEA), but also by other research organisations (for example the Laue-Langevin Institute (ILL), the ITER international organisation and the National Large Heavy Ion Accelerator – Ganil) or by industrial firms (for instance CIS bio international, Steris and Ionisos, which operate facilities producing radiopharmaceuticals, or industrial irradiators). These facilities also include projects to create fuel plants for Small Modular Reactors (SMRs). 1 – Research facilities and miscellaneous industrial facilities 1.1 Research reactors The purpose of research reactors is to contribute to scientific and technological research and to improve the operation of the Nuclear Power Plants (NPPs). Some of these facilities also produce radionuclides(1) for medical uses. They are facilities in which a chain reaction is created and sustained, to produce a neutron flux of varying density, used primarily for scientific experimentation purposes. Unlike in NPPs, the energy produced by research reactors is not used but simply removed by cooling. The quantities of radioactive substances used are smaller than in nuclear power reactors. An overview of the various types of research reactors in France and the main corresponding risks is presented below. In their design, these reactors take account of design basis accidents, both core melt “under water” (failure of the cooling system) and core melt “in air” (after uncovering of the core or during handling). They also take account of accidents specific to the particular design of certain research reactors. Neutron flux reactors Neutron flux reactors are pool-type reactors. They are mainly designed for fundamental research (solid physics, molecular physico-chemistry, biochemistry, etc.), using the neutron diffraction method to study matter. The neutrons are produced in the reactor, at different energy levels and are captured by channels in the reactor before being routed to experimentation areas. In France, only one neutron flux reactor is currently in operation: the High Flux Reactor (RHF – BNI 67) operated by the Laue-Langevin Institute (ILL) in Grenoble (rated power limited to 58 Megawatts thermal – MWth). The RHF operates in cycles of about 50 to 100 days. The main safety issues are reactivity control, cooling and containment. In 2025, the ILL continued the works to improve the safety of the RHF facility which were defined during the last periodic safety review. These works concern in particular the renovation of the polar crane in the reactor building, reinforcement of fire protection and removal of the residual tritium from the facility. In 2025, the ILL also sent ASNR the Guidance File for the facility’s next periodic safety review. This step, before the licensee sends the periodic safety review concluding report, expected by the end of 2027, serves to determine the methodology, the scope and the methods of the studies conducted as part of the forthcoming safety review. Finally, the ILL has entered into discussions with ASNR on the project to convert the reactor from a Highly-Enriched Uranium (HEU) fuel (>90% uranium-235) to a Low-Enriched Uranium (LEU) fuel (<20% uranium-235), targeted for 2030. “Test” reactors The “test” reactors are pool-type reactors. They are designed to study accident situations. They are able to reproduce certain accidents postulated in the safety case of nuclear power reactors in a controlled manner and on a small scale and gain a clearer understanding of the evolution of physical parameters during accidents. In France, only one “test” reactor is in operation: the Cabri reactor (BNI 24), operated by CEA in Cadarache. The reactor, whose power is limited to 25 MWth, can produce the neutron flux needed for the experiments. The safety issues are similar to those of the other reactors: controlling the reactivity of the driver core, cooling to remove heat and containment of the radioactive substances in the fuel rods making up the core. The CIP test programmes (Cabri International Programmes) on the Cabri “test” reactor came to an end in 2025 with the execution of the CIP3-1R test on 13 October 2025. CEA is now planning to start repair work on the hodoscope, authorised by the ASN in 2024. In 2025, in the light of the conclusions of its periodic safety review, ASNR also decided to make the continued operation of the reactor subject to compliance with requirements that oblige CEA to submit additional studies or justifications regarding the prevention of fire risks, risks associated with the dissemination of radioactive materials, and risks associated with earthquakes. Irradiation reactors The irradiation reactors are pool-type reactors. They are used to study the physical phenomena linked to the irradiation of materials and fuels, as well as their behaviour. As the neutron fluxes obtained by these facilities are more powerful than those in a Pressurised 330 ASNR Report on the state of nuclear safety and radiation protection in France in 2025
RkJQdWJsaXNoZXIy NjQ0NzU=