Initial results of swelling and irradiation creep interaction testing
An EBR-II irradiation test, designated as WSA-60, was established to provide swelling and irradiation creep interaction data when these two effects interact simultaneously in opposition. This type of behavior occurs under irradiation in cylindrical tubing containing an internal heat source and external heat sink. The WSA-60 test consists of encapsulated fuel pins wherein the capsules comprise the test samples. Slit tube data have been obtained on two 20% cold-worked AISI 316 stainless steel capsules irradiated to a peak fluence level of 2.2 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV). The capsules were irradiated to approximately the same fluence level and had similar temperature profiles. The slit tube data from the two capsules were observed to be self-consistent. Since the data are limited to low fluence levels where swelling is negligible the material behavior is dominated by irradiation creep effects. An assessment of the slit tube data was made by comparing the data with performance calculations using an irradiation creep equation formulated from pressurized tube data. The results show significant differences between the slit tube data and the calculations. A 34% reduction in irradiation creep was necessary to obtain consistency between the data and calculations. This difference is attributed to the following: (1) differences in material compositions between the slit tube and pressurized tube specimens; (2) the analytical methods used in irradiation creep equation development.
- OSTI ID:
- 5709837
- Report Number(s):
- CONF-820628-
- Journal Information:
- Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Vol. 782; Conference: 11. international symposium on effects of radiation on materials, American Society for Testing and Materials, Scottsdale, AZ, USA, 28 Jun 1982
- Country of Publication:
- United States
- Language:
- English
Similar Records
Irradiation creep and swelling of AISI 316 to exposures of 130 dpa at 385 to 400/sup 0/C
THE INFLUENCE OF COLD-WORK LEVEL ON THE IRRADIATION CREEP AND The Influence of Cold-Work Level on The Irradiation Creep and Swelling of AISI 316 Stainless Steel Irradiated as Pressurized Tubes In The EBR-II Fast Reactor
Related Subjects
STAINLESS STEEL-316
PHYSICAL RADIATION EFFECTS
CREEP
EBR-2 REACTOR
FAST NEUTRONS
FUEL PINS
SWELLING
TUBES
ALLOYS
BARYONS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FERMIONS
FUEL ELEMENTS
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRONS
NICKEL ALLOYS
NUCLEONS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
360106* - Metals & Alloys- Radiation Effects