High-burnup oxide fuel in European fast reactors

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6435276

Swanson, K M; Languille, A; Muhling, G

The European Collaboration on Fast Reactors is working on the design of a common demonstrate fast reactor, the European Fast Reactor (EFR) designed to be licensable in all the countries of the collaboration. The first consistent design of EFR calls for uranium-plutonium-oxide fuel assemblies. The first core target is a peak burnup of 15 at.% at a neutron displacement dose of 135 displacements per atom (dpa) NRT. The design targets for later charges are set at 20 at.% peak burnup and a 180-dpa NRT displacement dose. Achievement of these later burnup targets will reduce fuel cycle costs and increase reactor load factor by allowing a core life of {approximately}6 yr with a refueling cycle length of 2 yr. The research and development (R and D) requirement in the core and fuel area is to confirm that these EFR targets can be attained in the preferred pin and subassembly designs using candidate clad and wrapper materials. Assessment of the available information by core materials specialists in the collaboration leads to the conclusion that prime contenders for use as pin cladding are cold worked (CW) 15.15-Ti/1.4970 and PE16: for wrapper use, the martensitic steels, FV448/1.4914 and EM10 have been chosen. The oxide dispersion strengthened (ODS) ferritics are seen as an alternative option for clad use. The final choice for EFR rests on the irradiation performance of subassemblies using these alloys, particularly their ability to consistently reach the EFR targets for 180 to 220 dpa NRT and 20% burnup safely and without failure.

• OSTI ID: 6435276
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

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