Masurca research reactor – CEA centre The Masurca reactor (BNI 39), whose construction was authorised by a Decree of 14 December 1966, was intended for neutron studies, chiefly on the cores of fast neutron reactors, and the development of neutron measurement techniques. The reactor has been shut down since 2007. At the end of 2025, ASNR completed the first part of the review of the facility’s decommissioning dossier, which was submitted to the Minister responsible for nuclear safety in December 2020. The decommissioning of the facility is planned in four stages: completion of decommissioning preparation operations and removal of process equipment, decommissioning and remediation of general utilities and auxiliary technical installations, structural remediation and soil remediation. CEA plans to decommission the plant in nine years, while maintaining the existing buildings in a condition compatible with future use. Once the Ministry has drawn up an initial draft decree, scheduled for 2026, ASNR will issue an opinion on the text and prepare requirements governing the decommissioning. The decommissioning issues are limited in view of the significant reduction in the source term in the facility. The licensee is continuing the decommissioning preparation work. The dismantling of equipment in the nuclear buildings and the removal of experimental dosimeters were completed in 2025. The authorisation application file to modify the disposal of sodiumcontaining items is due to be submitted to ASNR at the end of 2025, and the disposal of source surplus to requirements began in 2025. These two operations are the last decommissioning preparation operations (OPDEM). The report concluding the review was submitted in April 2025 and ASNR has begun its review. ASNR considers that the level of nuclear safety and radiation protection, particularly with regard to the fight against external hazards and the management of deviations, maintenance and periodic inspections and tests inspected in 2025, is satisfactory. Éole and Minerve research reactors CEA centre The experimental reactors Éole and Minerve are very-low-power (less than one kilowatt) critical mock-ups that were used for neutron studies, in particular to evaluate the absorption of gamma rays or neutrons by materials. The Éole reactor (BNI 42), whose construction was authorised by a Decree of 23 June 1965, was intended primarily for neutron studies of moderated arrays, in particular those of PWRs and Boiling Water Reactors (BWRs). The Minerve reactor (BNI 95), whose transfer from the Fontenay‑aux‑Roses studies centre to the Cadarache studies centre was authorised by a Decree of 21 September 1977, is situated in the same hall as the Éole reactor. Teaching and research activities were carried out on these mock-ups until their final shutdown on 31 December 2017. Decree 2023-1176 of 12 December 2023 brought together the two BNIs 42 and 95 in a single BNI (BNI 42-U) called “Éole/Minerve”, and prescribed the decommissioning operations for this facility. During 2025, the licensee continued to characterise and dispose of the uranium-bearing materials present at the facility. ASNR considers that the level of safety and radiation protection at BNI 42-U is satisfactory overall. The annual inspection focused on four main areas: application of the new baseline safety requirements following the transition to decommissioning (resolution CODEPDRC-2024-049444 of 24 September 2024), criticality risk control, progress on the OPDEMs and the integrated management system. It confirmed that the characterisation and packaging operations are carried out in accordance with the authorisations for noteworthy modifications and are subject to appropriate traceability. ASNR is keeping a close eye on the finalisation of the OPDEMs that could not be completed before the application of decree 2023-1176 of 12 December 2023 prescribing the decommissioning of the facilities. The inspection also identified two main challenges: firstly, to improve traceability of deviations during physical material characterisation operations, particularly in the event of variations with data from the nuclear materials management system; and secondly, to update the facility’s procedures in accordance with the new decommissioning baseline requirements before the end of 2025. The Enriched Uranium Processing Facilities – CEA centre From 1963 to 1995, the Enriched Uranium Reprocessing Facilities (ATUe – BNI 52) converted uranium hexafluoride (UF6) from the Cadarache enrichment plants into sinterable oxide, and ensured the chemical reprocessing of waste from the manufacture of fuel elements. Decommissioning of this facility was authorised by Decrees in February 2006 and 2021, accompanied by ASN requirements describing the conditions of performance of the future decommissioning operations dated 14 October 2021. The activities in the facility in 2025 were essentially routine maintenance and periodic and regulatory inspection operations. These activities will continue until the decommissioning of the facility is complete. Decommissioning operations are currently scheduled to resume in 2028. The actions arising from the 2017 periodic safety review have been completed. Waterproofing work on the roof was completed in 2025. ASNR’s opinion on the orientation file for the next review, submitted in 2024, was sent to the licensee in May 2025. These factors will have to be taken into account when the report concluding the re-examination of the facility, due in 2027, is submitted. In 2025, the safety level of BNI 52 (ATUe) is satisfactory. Central Fissile Material Warehouse CEA centre Created in 1968, the Central Fissile Material Warehouse (MCMF – BNI 53) was a warehouse for storing enriched uranium and plutonium until its final shutdown and removal of all its nuclear materials on 31 December 2017. Its Decommissioning Decree was issued on 22 March 2024. It sets 31 December 2034 as the end-of-decommissioning deadline. ASNR considers that decommissioning operations continued satisfactorily in 2025. Remediation of the facility by surface cleaning has been planned for 2025 and will begin in 2026. The inspection relating to the report on the conclusion of the periodic safety review, submitted in 2024, which took place in 2025, revealed a robust organisation for implementing and monitoring the actions involved in this review. High-Activity Laboratory LECA‑STAR CEA centre BNI 55 combines the Active Fuel Examination Laboratory (LECA) and its extension, the Treatment, Clean-out and Reconditioning Station (STAR). These two units constitute CEA’s expert assessment tools for analysing irradiated fuels. Commissioned in 1964, the LECA laboratory enables CEA to carry out destructive and non-destructive examinations of irradiated fuel from the nuclear power, research and naval propulsion sectors. As the facility is old, it was partially reinforced in the early 2010s to improve its earthquake resistance. Provence-Alpes-Côte d’Azur 92 ABSTRACTS – ASNR Report on the state of nuclear safety and radiation protection in France in 2025
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