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Charpy impact test results of ferritic alloys at fluence to 6 x 10/sup 22/ n/cm

Technical Report ·
OSTI ID:6189199
One hundred and ten specimens made of HT-9 base metal, 9Cr-1Mo base metal and 9Cr-1Mo weldment at various heat treatment conditions were tested at -73 to 260/sup 0/C. The specimens were irradiated from 390 to 550/sup 0/C and the fluence of the specimens reached 6 x 10/sup 22/n/cm/sup 2/. Results show a small additional shift in transition temperature for HT-9 base metal irradiated at 390 and 450/sup 0/C as the fluence was raised to 6 x 10/sup 22/n/cm/sup 2/. At higher irradiation temperatures, however, the shift in transition temperature is less conclusive. Further reduction in USE was observed at higher fluence for all the irradiation temperatures. There is no apparent fluence effect for 9Cr-1Mo base metal at all the irradiation temperatures studied. Contrary to the previous finding on HT-9 base metal and weldment, the 9Cr-1Mo weldment shows a higher transition temperature (+60/sup 0/C) and a higher USE (+100%) as compared to the 9Cr-1Mo base metal for the same irradiation conditions. Significant improvement of both DBTT and USE on HT-9 base metal specimens fabricated from normalized and tempered plate stock was observed over the HT-9 base metal specimens fabricated from mill-annealed bar stock. Overall, the highest DBTT encountered for HT-9 alloys is 141/sup 0/C for specimens irradiated at 390/sup 0/C. The effect on transition temperature due to additional neutron exposure appears to be saturated at 6 x 10/sup 22/n/cm/sup 2/. The highest DBTT encountered for 9Cr-1Mo alloys, on the other hand, is 91/sup 0/C for the weldment and 45/sup 0/C for base metal both irradiated at 390/sup 0/C. 7 figures, 7 tables.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6189199
Report Number(s):
HEDL-7517; ON: DE85005718
Country of Publication:
United States
Language:
English