Large-diameter, high-plutonium metallic fuel testing in EBR-II
- Argonne National Lab., Idaho Falls, ID (United States)
The integral fast reactor (IFR) concept makes use of U-Pu-Zr metallic fuel alloys because of favorable core behavior characteristics and compatibility with a pyrometallurgical reprocessing scheme. Advanced reactor designs use U-x Pu-10 Zr (where 20 {le} x {le} 28). Most of the IFR fuel performance database was obtained with fuel containing {le}20 wt% Pu having a 0.439-cm diameter irradiated in cladding tubes having a 0.584-cm o.d. However, commercial implementations of the IFR concept (e.g., the advanced liquid-metal reactor by General Electric) will likely use fuel of larger diameter and plutonium contents {ge}20 wt%. The HT9 advanced driver fuel test, irradiated in Experimental Breeder Reactor II (EBR-II), was initiated to obtain irradiation performance data from larger diameter fuel cast with a range of plutonium compositions and clad in the reference cladding alloy HT9.
- OSTI ID:
- 89084
- Report Number(s):
- CONF-941102--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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