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Title: Phase Stability of an HT-9 Duct Irradiated in FFTF

Journal Article · · Journal of Nuclear Materials

A fuel test assembly known as ACO-3 duct made out of a fully tempered ferritic/martensitic steel (HT-9) was previously irradiated in the Fast Flux Test Reactor Facility (FFTF) up to 155 dpa at a temperature range of 380-504°C. The microstructures of the samples from 5 different zones along the face of the duct were analyzed using a combination of TEM based techniques, SANS and APT. A high density of Cr rich a' precipitates together with moderate density G-phase precipitates with an average sizes of 5 and 11 nm respectively were found at 20 dpa, 380°C zone. It was found that the precipitations of the second phases are more sensitive to temperature then the dose. In general, the density of both precipitates decreases with increasing irradiation temperature. No significant change is observed in average size of a' while the average size of G-phase precipitates increases up to 27 nm at 440°C. Voids are seen at 100 (410°C) and 155 (440°C) dpa zones but none was detected at 96 dpa (466°C) zone. In contrast to what is reported in the literature, no laves or Chi phases were found in any of the zones.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
DOE - NE
DOE Contract Number:
DE-AC07-05ID14517
OSTI ID:
1055348
Report Number(s):
INL/JOU-11-23837
Journal Information:
Journal of Nuclear Materials, Vol. 430, Issue 1 - 3; ISSN 0022-3115
Country of Publication:
United States
Language:
English

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