Auvergne‑Rhône‑Alpes Romans‑sur‑Isère site Framatome nuclear fuel fabrication plants On its Romans‑sur‑Isère site in the Drôme département, Framatome operates BNI 63-U, baptised “Nuclear fuel fabrication plant” resulting from the merging of two old BNIs, namely the unit fabricating fuel elements for research reactors (formerly BNI 63) and the unit fabricating nuclear fuel for the PWRs (formerly BNI 98). The fabrication of fuel for NPP reactors involves transforming UF6 into uranium oxide powder. The pellets fabricated from this powder in Framatome’s Romans‑sur‑Isère plant are placed in zirconium metal clads to constitute the fuel rods, then brought together to form the fuel assemblies to be used in the NPP reactors. In the case of experimental reactors, the fuels are more diverse, with some of them using, for example, highly-enriched uranium in metal form. These fuels are also fabricated in the Romans‑sur‑Isère plant called “Cerca”. At the Cerca plant, ASNR noted that the licensee is following proper procedure during their gradual transfer of production activities from the “uranium area” to the “new uranium area”, known as the NZU. The latter shows improved performance in terms of containment of the premises and the process, and risk prevention in the event of an extreme earthquake. In August 2025, the licensee declared a significant event concerning qualification of seismic anchors for equipment in the TRIGA unit, which remained in the old part of the Cerca plant; a specific action plan for remediation has been put in place to correct the deviations. In 2025, Framatome conducted further fuel production campaigns with Enriched Reprocessed Uranium (ERU). The request for substantial modification of the nuclear fuel manufacturing unit for PWRs, with the aim of increasing the production of ERU-based fuels, which was the subject of a public inquiry in February 2024, was authorised by Decree 2025-1186 of 8 December 2025. Based on the inspections it conducted in 2025, ASNR considers that the level of safety of the Framatome facilities is mixed. The start-up of the NZU is very positive, and the inspections carried out in 2025 by ASNR generally showed a good command of the processes monitored. Among the areas considered to be lagging behind, during the inspection ASNR noted significant deviations in the procedures for preparing fresh fuel transport packages. ASNR also noted shortcomings in the ageing management at the hydrofluoric acid condensation station, which led to closer monitoring by ASNR and a formal notice issued to Framatome on 8 July 2025. In early 2025, Framatome submitted an action plan to ASNR to reduce the amount of waste stored on the site. However, ASNR notes that by the end of 2025, the overall waste reduction process has not yet been initiated. In 2026, ASNR will therefore be closely monitoring completion of the proposed refurbishment of the hydrofluoric acid condensation station as well as the actual implementation of the proposed waste management measures. THE INDUSTRIAL AND RESEARCH FACILITIES High Flux Reactor of the Laue‑Langevin Institute The Laue-Langevin Institute (ILL), an international research organisation, accommodates a 58 Megawatt thermal (MWth) heavy-water High-Flux Neutron Reactor (RHF) which produces high-intensity thermal neutron beams for fundamental research, particularly in the areas of solid-state physics, neutron physics and molecular biology. The RHF constitutes BNI 67 and occupies a surface area of 12 hectares between the rivers Isère and Drac, upstream of their confluence, near the CEA Grenoble centre. From July 2024 to April 2025, the RHF was shut down to incorporate improvements following the latest safety review of the facility, including in particular the installation of a sprinkler fire extinguishing system in the reactor building’s experimental hall and seismic reinforcement of the polar crane in accordance with ASN resolution 2022-DC-0738 of 28 July 2022. After two irradiation cycles, a new shutdown began in October 2025 and is scheduled to continue until March 2026. This will make it possible to incorporate the latest safety improvements resulting from the last review. The reprocessing of the residual tritium inventory from the old detritiation facility, initially scheduled for 30 June 2025, has finally been delayed. An inspection carried out in December 2025 verified that the technically complex reprocessing facility was nearing completion and that the initial operating tests were conclusive. The licensee plans to start reprocessing in the first quarter of 2026. Lastly, the permits governing the RHF’s intakes and discharges were updated in 2025 by ASNR resolution 2025-DC-014 and 2025-DC015 of 26 June 2025. In view of the oversight actions it conducted in 2025, ASNR considers that the RHF is operated safely and radiation protection is satisfactory. In particular, ASNR emphasises the optimal way in which ILL has carried out the major programme of modifications to the facility following the last review, which has improved the RHF’s safety level. Ionisos irradiator The company Ionisos operates an industrial irradiator in Dagneux, situated in the Ain département. This irradiator, which constitutes BNI 68, uses the radiation from cobalt-60 sources for purposes such as sterilising medical equipment (syringes, dressings, prosthesis). In October 2021 the licensee filed an application for authorisation to build a new irradiator. This application is currently being examined by ASNR. The construction of this new facility also requires the licensee to finalise the Post-Operational Clean-Out (POCO) and dismantling of the site’s old irradiators D1 and D2. For several years now, in response to requests from ASNR, the licensee has been strengthening its teams and taking steps to better ensure that the facility complies with the BNI regulations. In 2025, although there is still room for improvement, ASNR considers that the licensee is in the process of making progress, which has resulted in particular in the definition and exhaustive implementation of periodic inspections and tests on protection important components. This improvement approach must be continued. 44 ABSTRACTS – ASNR Report on the state of nuclear safety and radiation protection in France in 2025
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