Impact Properties of Irradiated HT9 from the Fuel Duct of FFTF

Journal Article · Sun Jan 01 00:00:00 EST 2012 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2011.11.059· OSTI ID:1035525

Byun, Thak Sang ^[1]; Maloy, S ^[2]; Toloczko, M ^[3]; Lewis, William Daniel ^[1]

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1. ORNL
2. Los Alamos National Laboratory (LANL)
3. Pacific Northwest National Laboratory (PNNL)

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 oC. 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 25J capacity machine. Irradiation lowered the upper-shelf energy (USE) and increased the transition temperatures significantly. The shift of transition temperatures 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. For the irradiated specimens, 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. The size effect was also discussed to clarify the differences in the impact data of subsize and standard specimens.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1035525
• Journal Information: Journal of Nuclear Materials, Vol. 421, Issue 1-3; ISSN 0022-3115
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
CAPACITY
DIMENSIONS
DUCTS
FFTF REACTOR
IMPACT TESTS
IRRADIATION
ORIENTATION
RADIATION EFFECTS
TRANSITION TEMPERATURE
VELOCITY