Use of Subsize Fatigue Specimens for Reactor Irradiation Testing

Liu, KC; Grossbeck, M.L.

doi:10.1520/stp33010s

Cited by 5 publications

(1 citation statement)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…[2][3][4][5] The fatigue damage is induced by cyclic variations of pressure (stress), temperature and flow induced vibration, thereby reducing the lifetime of structures and components. [6][7][8] In order to understand the effects of stress ratio and environment temperature on the high-cycle fatigue behavior of type 316L stainless steel and its weld, the fatigue limits and the fracture modes were investigated at room temperature and 300 C. The subsize specimen [9][10][11] was also studied in this work. Comparisons were made between the data generated from subsize and standard specimens to examine the effect of specimen size on the fatigue behavior.…”

Section: Introductionmentioning

confidence: 99%

High-Cycle Fatigue Behavior of Type 316L Stainless Steel

et al. 2006

View full text Add to dashboard Cite

High-cycle fatigue tests were conducted to investigate the effects of temperature, stress ratio (R), specimen orientation, welding and specimen size on the fatigue behavior of type 316L stainless steel. The high-cycle fatigue test results indicated that the fatigue limits significantly decreased when the stress ratio (R) decreased. The corresponding fatigue limits were reduced to lower values when tests were conducted at 300 C, compared to those obtained at room temperature. The fatigue behavior and fatigue limits of standard and subsize specimens were observed to be consistent at both room temperature and 300 C. The constant life diagram was established from the S-N curves acquired. The fatigue limit strongly depended on the materials strength, which was a function of specimen orientation, test temperature, and welding processes. The dimension of the fatigue damaged area on a fracture surface increased as the stress ratio decreased. In the case of R ¼ À1:0, the fatigue damaged region extended over the whole fracture surface. The subgrain boundaries after high-cycle fatigue tests were clearly demonstrated by their diffraction patterns, which were related to the dynamic recovery of multiple dislocations.

show abstract

Section: Introductionmentioning

confidence: 99%

High-Cycle Fatigue Behavior of Type 316L Stainless Steel

et al. 2006

View full text Add to dashboard Cite

show abstract

Fatigue behavior of irradiated helium-containing ferritic steels for fusion reactor applications

Grossbeck

Vitek

Liu

1986

Journal of Nuclear Materials

View full text Add to dashboard Cite

The martensitic alloys 12Cr-lMoVW and 9Cr-lMoVNb have been irradiated in the High Flux Isotope Reactor (HFIR) and subsequently tested in fatigue. In order to achieve helium levels characteristic of fusion reactors, the 12Cr-lMoVW was doped with 1 and 2% Ni, resulting in helium levels of 210 and 410 at. ppm at damage levels of 25 dpa. The 9Cr-lMoVNb was irradiated to a damage level of 3 dpa and contained <5 at. ppm He. Irradiations were carried out at 55°C and testing at 22°C. No significant changes were found in 9Cr-lMoVNb upon irradiation at this damage level, but effects that could possibly be attributed to helium were found in 12Cr-lMoVW. Levels of 210 and 410 at. ppm He produced cyclic strengthening of 29 and 34% over unirradiated nickel-doped materials, respectively. This cyclic hardening attributable largely to helium resulted in degradation of the cyclic life. However, the fatigue life remained comparable to or better than unirradiated 20%-coId-worked 316 stainless steel.

show abstract