High Strain Fatigue Properties of the F82H Ferritic-Martensitic Steel under Proton Irradiation.
- Plasma Physics Reseach Center of Switzerland/Ecole Polytechnique Federale de Lausanne, Paul Scherrer
- BATTELLE (PACIFIC NW LAB)
During the up and down cycles of a fusion reactor, the first wall is exposed concomitantly to a flux of energetic neutrons that generates radiation defects and to a neutron thermal flux that induces thermal stresses. The resulting strains may exceed the elastic limit and induce a plastic deformation in the material. A similar situation occurs in the window of a spallation liquid source target and results in the same type of damage. This particular loading has been simulated in F82H martensitic ferritic steel, using a device allowing a fatigue test to be carried out during irradiation with 590 MeV protons. All fatigue tests were carried out at 300?C, in a strain controlled test at strain levels around 0.8%. Two different signals have been used: a fully symmetrical triangle wave signal (R=-1) and a triangle ramp with 2 min tension holds. The fatigue was investigated under three different conditions: unirradiated , irradiated and post irradiation tested, and finally in beam tested. The main result is that the in beam tested specimens have the lowest life as compared to the post irradiation tested specimens and unirradiated specimens. Hydrogen is suspected to be the main contributor to the observed embrittlement.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 15003873
- Report Number(s):
- PNNL-SA-37191; TRN: US1005099
- Journal Information:
- Journal of Nuclear Materials, 318(132-142, Vol. 318; ISSN 0022-3115
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fatigue performance and cyclic softening of F82H, a ferritic martensic steel
Influence of fatigue precracking and specimen size on Master Curve fracture toughness measurements of EUROFER97 and F82H steels
Related Subjects
08 HYDROGEN
DEFECTS
DEFORMATION
EMBRITTLEMENT
FERRITIC STEELS
FIRST WALL
HYDROGEN
IRRADIATION
NEUTRONS
PLASTICS
PROTONS
RADIATIONS
SPALLATION
STEELS
STRAINS
TARGETS
THERMAL STRESSES
THERMONUCLEAR REACTORS
Ferritic Martensitic Steel
Mechanical Properties
Radiation Effects
Helium Generation
Hydrogen Generation