Characterization of metal fuel fragmentation
While the Integral Fast Reactor (IFR) employs a metal-alloy fuel design which has inherent safety features, a complete analysis of reactor safety requires assessment of the consequences of the melting of uranium alloy fuel in the core and the contact of molten core materials with sodium. A series of eight tests was therefore conducted in which the fragmentation and interaction behavior of kilogram quantities of uranium-zirconium alloy in sodium was studied.
- Research Organization:
- Argonne National Lab., IL (United States). Reactor Analysis and Safety Div.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 712403
- Report Number(s):
- ANL-IFR--52; ON: TI86027325
- Country of Publication:
- United States
- Language:
- English
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