Recent improvements in size effects correlations for DBTT and upper shelf energy of ferritic steels
Conference
·
OSTI ID:5222300
- Missouri Univ., Rolla, MO (United States)
- Pacific Northwest Lab., Richland, WA (United States)
Currently available correlations for the effects of specimen size on the USE were developed for relatively ductile steels and will not serve as well when the steels become embrittled. Size effects correlations were developed recently for the impact properties of less ductile HT9 to be applied to other initially more ductile steels as they lose their ductility during irradiation. These new correlations successfully predict the ductile brittle transition temperature (DBTT) and the upper shelf energy (USE) of full size Charpy specimens based on subsize specimen data. The new DBTT and the USE correlations were tested against published experimental data on other ferritic steels and shown to perform successfully at lower USE particularly when both precracked and notched only specimens were employed.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5222300
- Report Number(s):
- PNL-SA-19683; CONF-920146--3; ON: DE92014703
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420500 -- Engineering-- Materials Testing
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480* -- Fusion Technology-- Component Development
ALLOYS
CHARPY TEST
CONTAINERS
DAMAGING NEUTRON FLUENCE
DESTRUCTIVE TESTING
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
FERRITIC STEELS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MODIFICATIONS
Ma
Materials Studies-- (1992-)
NEUTRON FLUENCE
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
STEELS
TESTING
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION TEMPERATURE
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420500 -- Engineering-- Materials Testing
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480* -- Fusion Technology-- Component Development
ALLOYS
CHARPY TEST
CONTAINERS
DAMAGING NEUTRON FLUENCE
DESTRUCTIVE TESTING
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
FERRITIC STEELS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
MODIFICATIONS
Ma
Materials Studies-- (1992-)
NEUTRON FLUENCE
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
STEELS
TESTING
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION TEMPERATURE