Fast reactor fuel and material research in Phenix - A fuel cycle assay

Conference · Mon Jan 01 00:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6933945

Chaumont, J M; Savineau, M ^[1]

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1. CEA, Bagnols (France)

One of the goals for Phenix is to demonstrate the ability of fast reactors to operate on an economical fuel cycle. This means, among other things, that it is possible (a) to achieve a proper design for fuel elements that can withstand large enough burnup values and (b) to close the fuel cycle through reprocessing in such a way that the cycle need be fed only with depleted uranium. Achieving high fuel-element burnup values on Phenix was possible with the help of three techniques: (1) proper selection of the cladding and hexagonal wrapper alloys in order to choose steel alloys that do not swell or creep under irradiation; (2) accurate monitoring of core element behavior under irradiation; (3) hot cells directly connected to the storage drum are used to measure and monitor geometric changes of both whole assemblies and individual pins. With these various techniques, the burnup of both experimental and standard fuel elements has been continuously increased from the initial value of [approximately] 50,000 MWd/t up to the current maximum value of 136,000 MWd/t. Phenix fuel has been reprocessed since 1977 at either La Hague or Marcoule, and the recovered plutonium has been fed into the fabrication of new assemblies since 1980. It has been demonstrated that a fast reactor fuel cycle can be closed and need be fed only with depleted uranium. From 1980 to 1985, the fuel cycle was maintained in equilibrium, the total amount of plutonium being [approximately] 3.5 t:1 t in the reactor and 2.5 t circulating outside the reactor between decay heat time, reprocessing, and refabrication.

• OSTI ID: 6933945
• Report Number(s): CONF-901101-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 62; Conference: American Nuclear Society (ANS) winter meeting, Washington, DC (United States), 11-16 Nov 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PHENIX REACTOR
FUEL CYCLE
ACCURACY
AFTER-HEAT REMOVAL
BURNUP
DEPLETED URANIUM
DESIGN
ECONOMICS
FABRICATION
FUEL CANS
FUEL ELEMENTS
IN CORE INSTRUMENTS
PHYSICAL RADIATION EFFECTS
PLUTONIUM RECYCLE
REACTOR CORES
REACTOR MONITORING SYSTEMS
REPROCESSING
ACTINIDES
BREEDER REACTORS
ELEMENTS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
PLUTONIUM REACTORS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR INSTRUMENTATION
REACTORS
REMOVAL
SEPARATION PROCESSES
SODIUM COOLED REACTORS
URANIUM
210500* - Power Reactors
Breeding