Steel impurity element effects on postirradiation properties recovery by annealing: Final report
The influence of copper content and phosphorus content on notch ductility recovery by 399/degree/C postirradiation heat treatment was explored for A 533-B and A 302-B pressure vessel steels. Charpy-V (C/sub v/) specimens for the investigation were obtained from ten plates produced from four (4-way split) laboratory melts. The plates were heat treated to reproduce the microstructure of 150-mm and thicker A 302-B plates at the quarter-thickness location. Specimens were irradiated at 288/degree/C (550/degree/F) to a fluence of /approximately/2.5 /times/ 10/sup 19/ n/cm/sup 2/ in the UBR test reactor. Other specimens were thermally conditioned at 288/degree/C and at 288/degree/C followed by 399/degree/C to benchmark the effects of temperature in the absence of irradiation. A 0.30% copper content was found to have a significant influence on the magnitude of residual embrittlement after a 168-hour anneal. In contrast, phosphorus contents in the range of 0.002 to 0.025% were not found to have an effect on notch ductility recovery for either a high or a low copper content. Essentially full recovery in 41-J transition temperature was observed for the high phosphorus, low copper content steel versions. A detrimental influence of a 0.68% nickel content on recovery behavior is shown by the data for the 0.28% copper content plates but not the 0.16% copper content plates. 13 refs., 16 figs., 4 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Materials Engineering Associates, Inc., Lanham, MD (USA)
- OSTI ID:
- 5890126
- Report Number(s):
- NUREG/CR-5388; MEA-2354; ON: TI89015595
- Country of Publication:
- United States
- Language:
- English
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Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels
Significance of nickel and copper content to radiation sensitivity and postirradiation heat-treatment recovery of reactor-vessel steels
Related Subjects
COPPER
METALLURGICAL EFFECTS
PHOSPHORUS
STEEL-ASTM-A533-B
PHYSICAL RADIATION EFFECTS
AGING
ANNEALING
CHARPY TEST
DUCTILITY
EMBRITTLEMENT
HEAT TREATMENTS
IMPURITIES
IRRADIATION
NEUTRON FLUENCE
PROGRESS REPORT
REACTOR VESSELS
TENSILE PROPERTIES
ALLOYS
CARBON STEELS
CONTAINERS
DESTRUCTIVE TESTING
DOCUMENT TYPES
ELEMENTS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALS
NONMETALS
RADIATION EFFECTS
STEELS
TESTING
TRANSITION ELEMENTS
360106* - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties