Apparent embrittlement saturation and radiation mechanisms of reactor pressure vessel steels
The irradiation and annealing results of three different reactor pressure vessel steels are reported. Steel A, a basic material according to ASTM A-533 B having 0.15 percent vanadium; and Steel C contained 3.2 percent nickel. The steels were irradiated at 150, 300, and 400 degree C with neutron fluxes of 6 multiplied by 10/sup 11/ and 3 multiplied by 10/sup 13/ neutrons (n)/cm/sup 2//s. An apparent saturation-in-irradiation effect was found within certain neutron fluence ranges. During the annealing, various recovery processes occur in different temperature ranges. These are characterized by various activation energies. The individual processes were determined by the different time dependencies at various temperatures. Two causes for the apparent saturation were discovered from the behavior of the annealing curves.
- Research Organization:
- Nucl Res Cent Juelich, Ger
- OSTI ID:
- 6453690
- Report Number(s):
- CONF-800609-
- Journal Information:
- Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Conference: 10. international symposium on effects of radiation on materials, Savannah, GA, USA, 3 Jun 1980
- Country of Publication:
- United States
- Language:
- English
Similar Records
Refinements to pressure vessel steel embrittlement correlations
Neutron damage in reactor pressure-vessel steel examined with positron annihilation lifetime spectroscopy
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
PRESSURE VESSELS
EMBRITTLEMENT
PHYSICAL RADIATION EFFECTS
STEEL-ASTM-A533
ANNEALING
CHARPY TEST
REACTOR MATERIALS
REACTOR VESSELS
ALLOYS
CONTAINERS
DESTRUCTIVE TESTING
HEAT TREATMENTS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
RADIATION EFFECTS
STEELS
TESTING
360106* - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties
220200 - Nuclear Reactor Technology- Components & Accessories