Steel impurity element effects on postirradiation properties recovery by annealing: Final report
Technical Report
·
OSTI ID:5890126
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
Similar Records
Significance of copper, phosphorus, and sulfur content to radiation sensitivity and postirradiation heat treatment of A302-B steel. Final report
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
Technical Report
·
Wed Apr 11 23:00:00 EST 1979
·
OSTI ID:5509785
Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:5836190
Significance of nickel and copper content to radiation sensitivity and postirradiation heat-treatment recovery of reactor-vessel steels
Technical Report
·
Sun Oct 31 23:00:00 EST 1982
·
OSTI ID:6618279
Related Subjects
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
AGING
ALLOYS
ANNEALING
CARBON STEELS
CHARPY TEST
CONTAINERS
COPPER
DESTRUCTIVE TESTING
DOCUMENT TYPES
DUCTILITY
ELEMENTS
EMBRITTLEMENT
HEAT TREATMENTS
IMPACT TESTS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALLURGICAL EFFECTS
METALS
NEUTRON FLUENCE
NONMETALS
PHOSPHORUS
PHYSICAL RADIATION EFFECTS
PROGRESS REPORT
RADIATION EFFECTS
REACTOR VESSELS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES
TESTING
TRANSITION ELEMENTS
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
AGING
ALLOYS
ANNEALING
CARBON STEELS
CHARPY TEST
CONTAINERS
COPPER
DESTRUCTIVE TESTING
DOCUMENT TYPES
DUCTILITY
ELEMENTS
EMBRITTLEMENT
HEAT TREATMENTS
IMPACT TESTS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALLURGICAL EFFECTS
METALS
NEUTRON FLUENCE
NONMETALS
PHOSPHORUS
PHYSICAL RADIATION EFFECTS
PROGRESS REPORT
RADIATION EFFECTS
REACTOR VESSELS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES
TESTING
TRANSITION ELEMENTS