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Title: Summary of Post Irradiation Examination Results of the AFIP-6 Failure

Conference ·
OSTI ID:1044198

The AFIP-6 test assembly was irradiated for one cycle in the Advanced Test Reactor at Idaho National Laboratory. The experiment was designed to test two monolithic fuel plates at power and burn-ups which bounded the operating conditions of both ATR and HFIR driver fuel. Both plates contain a solid U-Mo fuel foil with a zirconium diffusion barrier between 6061-aluminum cladding plates bonded by hot isostatic pressing. The experiment was designed with an orifice to restrict the coolant flow in order to obtain prototypic coolant temperature conditions. While these coolant temperatures were obtained, flow restriction resulted in low heat transfer coefficients and the failure of the fuel plates. The results from the post irradiation examinations and some observations of the failure mechanisms are outlined herein.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
DOE - NA
DOE Contract Number:
DE-AC07-05ID14517
OSTI ID:
1044198
Report Number(s):
INL/CON-11-23853; TRN: US1203353
Resource Relation:
Conference: RERTR 2011,Santiago, Chile,10/23/2011,10/27/2011
Country of Publication:
United States
Language:
English