Impact properties of irradiated HT9 from the fuel duct of FFTF

Journal Article · Wed Feb 01 00:00:00 EST 2012 · Journal of Nuclear Materials, 421(1 - 3):104 - 111

DOI:https://doi.org/10.1016/j.jnucmat.2011.11.059· OSTI ID:1037511

Byun, Thak Sang; Lewis, W Daniel; Toloczko, Mychailo B; Maloy, Stuart A

This paper reports Charpy impact test data for the ACO-3 duct material (HT9) from the Fast Flux Test Facility (FFTF) and its archive material. Irradiation doses for the specimens were in the range of 3– 148 dpa and irradiation temperatures in the range of 378–504 *C. The impact tests were performed for the small V-notched Charpy specimens with dimensions of 3 * 4 * 27 mm at an impact speed of 3.2 m/s in a 25 J capacity machine. Irradiation lowered the upper-shelf energy (USE) and increased the transition temperatures significantly. The shift of ductile–brittle transition temperatures (DDBTT) was greater after relatively low temperature irradiation. The USE values were in the range of 5.5–6.7 J before irradiation and decreased to the range of 2–5 J after irradiation. Lower USEs were measured for lower irradiation temperatures and specimens with T-L orientation. The dose dependences of transition temperature and USE were not significant because of the radiation effect on impact behavior nearly saturated at the lowest dose of about 3 dpa. A comparison showed that the lateral expansion of specimens showed a linear correlation with absorbed impact energy, but with large scatter in the results. Size effect was also discussed to clarify the differences in the impact property data from subsize and standard specimens as well as to provide a basis for comparison of data from different specimens. The USE and DDBTT data from different studies were compared.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1037511
• Report Number(s): PNNL-SA-85024; AF5810000
• Journal Information: Journal of Nuclear Materials, 421(1 - 3):104 - 111, Vol. 421, Issue 1-3; ISSN 0022-3115
• Country of Publication: United States
• Language: English