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Microstructural Characterization of High Dose Irradiated HT9

Technical Report ·
DOI:https://doi.org/10.2172/1565803· OSTI ID:1565803
The present report provides a short summary of the recent efforts to irradiate various HT9 heats and compositions to a high damage level (>500 peak dpa) and characterize the changes to the microstructure. The majority of the data reported here will focus on characterizing the “INL” HT9 heat. This particular heat was chosen due to its high volume fraction of tempered martensite (>90%) in the microstructure. The results show that very little swelling is present in INL HT9 up to doses up to 600 peak dpa. Voids are only observed in the near surface region. Some carbides are also observed to accompany the irradiation. Comparison of void swelling with published neutron irradiation shows good agreement. Additional investigations into the response of delta ferrite grains show a very different distribution of voids and significantly higher void swelling compared to the tempered martensite grains.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign
DOE Contract Number:
89233218CNA000001
OSTI ID:
1565803
Report Number(s):
LA-UR--19-29126
Country of Publication:
United States
Language:
English

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