Low cycle fatigue properties of neutron irradiated solid HIP 316L(N). ITER Task T214, NET deliverable GB6 ECN-5
Description
The Low Cycle Fatigue (LCF) properties of neutron irradiated Hot Isostatically Pressed (HIP) joints of type 316L(N) stainless steel (heat PM-130) have been measured, as well as the LCF properties of reference 316L(N)-ERHII. Cylindrical LCF test specimens of 3 mm diameter were irradiated in the High Flux Reactor (HFR) in Petten, The Netherlands, simulating the first wall conditions of future fusion reactors by a combination of high displacement damage with proportional amounts of helium. The solid HIP specimens were irradiated up to a target dose level of 5 dpa at a temperature of 550K. The damage levels realised range from 3.0 to 4.4 dpa, with helium contents up to 41 appm. Testing temperature was equal to the irradiation temperature: 550K. The report contains the experimental conditions and summarises the results, which are given in terms of first cycle stress, the peak stress, the number of cycles where the peak stress is reached, the stress at half life and the plastic strain at half life, and the total number of cycles to failure, Nf. The main conclusions are that the unirradiated solid-HIP materials has the same LCF properties as unirradiated 316L(N)-ERHII plate material. The neutron irradiation induces both hardening and reduction of fatigue life. The bond does not seem to have any effect on the fatigue properties for the unirradiated solid HIP 316L(N), whereas a combined effect of irradiation and the bond cannot be established. No failures related to debonding of the joint were observed for the tests. 7 refs
Availability note (English)
Available from the library at the Netherlands Energy Research Foundation (ECN), P.O. Box 1, 1755 ZG Petten (NL)Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- ECN-C--98-034
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 29048354
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ATOMIC DISPLACEMENTS; BREEDING BLANKETS; DUCTILITY; FATIGUE; FIRST WALL; HARDENING; HELIUM; HFR REACTOR; HOT PRESSING; ITER TOKAMAK; JOINTS; POST-IRRADIATION EXAMINATION; STAINLESS STEEL-316L; STRAINS; STRESSES; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CLOSED PLASMA DEVICES; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS TESTING REACTORS; MATERIALS WORKING; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; PHYSICAL RADIATION EFFECTS; PRESSING; RADIATION EFFECTS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TENSILE PROPERTIES; THERMAL REACTORS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Project ECN 7.1103
- Notes
- The work reported is carried out within the framework of the European Fusion Technology Programme