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| PHENIX (reactor) | |
|---|---|
| Name | PHENIX |
| Country | France |
| Operator | Commissariat à l'énergie atomique et aux énergies alternatives |
| Status | Decommissioned |
| Construction began | 1968 |
| Commissioned | 1973 |
| Decommissioned | 2010 (shutdown 2009) |
| Reactor type | Fast breeder reactor |
| Coolant | Liquid sodium |
| Electrical capacity | 250 MW |
PHENIX (reactor) was a French liquid‑metal fast breeder reactor operated by the Commissariat à l'énergie atomique et aux énergies alternatives near Marcoule, Gard, France. Designed during the Cold War era to advance breeder technology and plutonium management, PHENIX contributed to research in fast neutron physics, fuel reprocessing, and sodium coolant engineering while interacting with programs in United Kingdom, United States, Soviet Union, Japan, and Germany.
PHENIX was a pool‑type, sodium‑cooled fast breeder reactor designed to test concepts related to the Fast breeder reactor class, incorporating features influenced by designs such as BN-350, Monju, Superphénix, and experimental reactors including EBR-II and Dounreay Fast Reactor. The plant operated at an electrical output of about 250 MW and a thermal power around 560 MW, using mixed oxide fuel derived from plutonium and uranium, similar to materials handled in Mayak Production Association and La Hague. Its core and control systems leveraged experience from naval projects like S5 G reactor development and civil prototypes in United Kingdom Atomic Energy Authority programs. PHENIX used a primary and secondary loop of liquid sodium with an intermediate heat exchanger linked to steam generators comparable to those in designs studied by Argonne National Laboratory, CEA, and Westinghouse Electric Company for heat transport and turbine coupling.
Construction began in the late 1960s, with criticality achieved in 1973 and commercial operation following, paralleling milestones in Nuclear power in France and the broader European nuclear expansion led by entities such as Électricité de France and the European Commission research initiatives. PHENIX operated through the 1970s and 1980s, contributing data to international collaborations involving International Atomic Energy Agency, Organisation for Economic Co‑operation and Development Nuclear Energy Agency, and bilateral exchanges with programs in Japan Atomic Energy Agency, United States Department of Energy, and Russian Academy of Sciences. Throughout its operational lifetime PHENIX supported experiments on fuel irradiation, materials testing, and transient behavior comparable to studies carried out at Oak Ridge National Laboratory, Idaho National Laboratory, and Kurchatov Institute. The reactor's operation was periodically suspended for maintenance, refurbishment, and regulatory review influenced by events like the Three Mile Island accident and the Chernobyl disaster, culminating in final shutdown decisions in the 2000s under oversight from the Nuclear Safety Authority (France).
PHENIX incorporated passive and active safety systems typical of sodium‑cooled fast reactors, including multiple independent shutdown systems, diverse decay heat removal paths, and sodium leak detection methods analogous to those developed at CEA facilities and tested by United Kingdom Atomic Energy Authority and Argonne National Laboratory. The reactor's sodium coolant necessitated specialized fire suppression and inerting infrastructure comparable to measures implemented after incidents at facilities like Monju and Dounreay. During its service PHENIX experienced operational incidents and scrams that prompted investigations by regulators such as the Autorité de sûreté nucléaire and reviews by international bodies like the International Atomic Energy Agency. Lessons from these events informed revisions to emergency planning influenced by protocols in United States Nuclear Regulatory Commission and post‑accident reforms paralleling those after the Fukushima Daiichi nuclear disaster.
PHENIX used mixed oxide (MOX) fuel, connecting its fuel cycle to reprocessing capabilities and plutonium management strategies associated with facilities like La Hague and industrial partners including AREVA (now part of Framatome and Orano). Irradiated fuel handling involved cooling, inspection, and reprocessing research comparable to programs at Sellafield and Mayak, with wastes categorized and managed under French regulations influenced by laws such as the French radioactive waste management law. High‑level waste, transuranic elements, and activated structural materials were characterized for conditioning, storage, and eventual repository concepts similar to proposals evaluated by ANDRA and international repositories like Onkalo in Finland. PHENIX contributed experimental data to partitioning and transmutation studies pursued by OECD/NEA and national research institutes to reduce long‑term radiotoxicity and optimize closed fuel cycle strategies championed by policymakers in France and partners in the European Union.
Following permanent shutdown, PHENIX entered a staged decommissioning process managed by the Commissariat à l'énergie atomique et aux énergies alternatives with oversight from the Autorité de sûreté nucléaire. Decommissioning activities involved sodium draining, coolant cleaning, fuel removal, and segmentation of activated components, drawing on methodologies developed at sites such as Sellafield, Idaho National Laboratory, and Dounreay. The reactor's legacy includes technical reports, experimental databases, and personnel expertise that informed contemporary fast reactor projects like ASTRID, proposals by private firms, and international efforts in advanced reactors promoted at forums such as the Generation IV International Forum and GIF. PHENIX's operational experience influenced policy debates in France regarding plutonium reuse, energy strategy, and research priorities amid transitions involving renewable energy targets and European energy security discussions. Its archives and decommissioning program continue to serve as a resource for engineers and regulators from institutions including University of California, Imperial College London, Moscow Engineering Physics Institute, and national laboratories worldwide.
Category:Fast breeder reactors Category:Nuclear reactors in France Category:Decommissioned nuclear reactors