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Title: Thermal stability of fission gas bubble superlattice in irradiated U–10Mo fuel

To investigate the thermal stability of the fission gas bubble superlattice, a key microstructural feature in both irradiated U-7Mo dispersion and U-10Mo monolithic fuel plates, a FIB-TEM sample of the irradiated U-10Mo fuel with a local fission density of 3.5×1021 fissions/cm3 was used for an in-situ heating TEM experiment. The temperature of the heating holder was raised at a ramp rate of approximately 10 ºC/min up to ~700 ºC, kept at that temperature for about 34 min, continued to 850 ºC with a reduced rate of 5 ºC/min. The result shows a high thermal stability of the fission gas bubble superlattice. The implication of this observation on the fuel microstructural evolution and performance under irradiation is discussed.
Authors:
 [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1182222
Report Number(s):
INL/JOU--14-33997
Journal ID: ISSN 0022-3115; TRN: US1500194
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 464; Journal Issue: C
Publisher:
Elsevier
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; GASES; FISSION PRODUCTS; TRANSMISSION ELECTRON MICROSCOPY; IRRADIATION; BUBBLES; STABILITY; SUPERLATTICES; FUEL PLATES; DENSITY; HEATING; MICROSTRUCTURE; DISPERSION NUCLEAR FUELS; PERFORMANCE; URANIUM BASE ALLOYS; MOLYBDENUM ALLOYS; BINARY ALLOY SYSTEMS; TEMPERATURE RANGE 0400-1000 K BUBBLE SUPERLATTICE; FISSION GAS; TEM IN-SITU HEATING; THERMAL STABILITY; U-10MO FUEL