Published July 1991 | Version v1
Report Open

Reliability of fast reactor mixed-oxide fuel during operational transients

  • 1. Argonne National Lab., IL (United States)
  • 2. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

Description

Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 figs., 4 tabs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE91018633; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
28 p.
Report number
ANL/CP--73613

Conference

Title
International conference on fast reactor systems and fuel cycles.
Dates
27 Oct - 1 Nov 1991.
Place
Kyoto (Japan).

Optional Information

Contract/Grant/Project number
Contract W-31109-ENG-38
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-911001--18.