Phénix: Difference between revisions

Latest revision as of 11:33, 15 February 2025

Phénix (nuclear reactor)[edit]

The Phénix was a sodium-cooled fast breeder reactor located at the Marcoule Nuclear Site in France. It was a prototype reactor designed to demonstrate the feasibility of fast breeder technology, which aims to generate more fissile material than it consumes.

Design and Construction[edit]

The Phénix reactor was constructed in the late 1960s and became operational in 1973. It was designed to use plutonium as its primary fuel and sodium as a coolant. The reactor had a thermal power output of 563 MW and an electrical output of 250 MW.

Operation[edit]

Phénix operated successfully for several decades, contributing to research in fast breeder technology and providing valuable data on the operation of sodium-cooled reactors. It was used to test various nuclear fuel types and configurations.

Decommissioning[edit]

The reactor was shut down in 2009 after 36 years of operation. The decommissioning process involves dismantling the reactor and safely managing the radioactive materials.

Related pages[edit]

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-'''Phénix''' is a [[nuclear reactor]] that was operational in [[France]] from 1973 to 2009. It was a [[fast breeder reactor]], a type of reactor designed to produce more [[fissile material]] than it consumes, thus "breeding" fuel. Phénix was part of the French government's long-term strategy for energy independence, which included the development of a closed nuclear fuel cycle where spent fuel would be reprocessed and reused.
+{{DISPLAYTITLE:Phénix (nuclear reactor)}}
-== History ==
+== Phénix (nuclear reactor) ==
+[[File:Marcoule_seen_of_CDC.JPG|thumb|right|Aerial view of the Marcoule Nuclear Site, where Phénix is located.]]
+The '''Phénix''' was a [[sodium-cooled fast breeder reactor]] located at the [[Marcoule Nuclear Site]] in [[France]]. It was a prototype reactor designed to demonstrate the feasibility of fast breeder technology, which aims to generate more [[fissile material]] than it consumes.
-Phénix was constructed in the early 1970s as part of a French government initiative to develop a [[nuclear power]] industry that could provide the country with a reliable and independent source of energy. The reactor was designed and built by the [[Commissariat à l'énergie atomique et aux énergies alternatives|French Atomic Energy Commission]] (CEA), and it began operation in 1973.
+=== Design and Construction ===
+The Phénix reactor was constructed in the late 1960s and became operational in 1973. It was designed to use [[plutonium]] as its primary fuel and [[sodium]] as a coolant. The reactor had a thermal power output of 563 MW and an electrical output of 250 MW.
-Over its 36 years of operation, Phénix produced a significant amount of electricity for the French grid and contributed to the development of the country's nuclear industry. The reactor was also used for research purposes, particularly in the field of [[nuclear transmutation]], a process that can reduce the volume and toxicity of nuclear waste.
+=== Operation ===
+Phénix operated successfully for several decades, contributing to research in fast breeder technology and providing valuable data on the operation of sodium-cooled reactors. It was used to test various [[nuclear fuel]] types and configurations.
-Phénix was shut down in 2009, and it is currently in the process of being decommissioned. The lessons learned from its operation have been used in the design of the [[Astrid (reactor)|Astrid]] project, a new generation of fast breeder reactors.
+=== Decommissioning ===
+The reactor was shut down in 2009 after 36 years of operation. The decommissioning process involves dismantling the reactor and safely managing the radioactive materials.
-== Design and operation ==
+== Related pages ==
+* [[Nuclear reactor]]
+* [[Fast breeder reactor]]
+* [[Sodium-cooled reactor]]
+* [[Marcoule Nuclear Site]]
-Phénix was a [[sodium-cooled fast reactor]], a type of fast breeder reactor that uses liquid sodium as a coolant. This design allows the reactor to operate at high temperatures and makes it possible to use a wide range of fuels, including [[plutonium]] and [[minor actinides]].
+[[Category:Nuclear reactors in France]]
+[[Category:Fast breeder reactors]]
-The reactor had a thermal power of 590 MW and an electrical power of 233 MW. It used a mixed oxide (MOX) fuel, which is a blend of plutonium and natural or depleted uranium. The fuel was arranged in a core surrounded by a blanket of fertile material, which could be converted into fissile material by the neutrons produced in the core.
-== Legacy ==
-The operation of Phénix provided valuable experience and data for the French nuclear industry. It demonstrated the feasibility of fast breeder reactors and contributed to the development of the closed nuclear fuel cycle in France. The lessons learned from Phénix have been used in the design of the Astrid project, which aims to develop a new generation of fast breeder reactors.
-[[Category:Nuclear reactors]]
-[[Category:Nuclear energy in France]]
-{{France-energy-stub}}
-{{Nuclear-technology-stub}}