Effect of dynamic strain aging on the low cycle fatigue in SA508 C1.3 reactor pressure vessel steel = SA508 C1.3 원자로압력용기강에서 동적 변형시효가 저주파피로에 미치는 영향

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 421
  • Download : 0
The effect of dynamic strain aging on cyclic stress response and fatigue life of ASME SA508 Cl.3 forging steel for nuclear reactor pressure vessels was studied at temperatures ranging from room temperature to 500℃. Total strain ranges and strain rates were varied from 0.7 to 2.0% and from $1×10^{-2}$ to $4×10^{-4}s^{-1}$, respectively. Test environments were the atmospheres of air and argon. Except for the temperature region of dynamic strain aging, 300℃, the initial cyclic hardening was immediately followed by cyclic softening at all strain rates in air atmosphere. The cyclic softening continued over 95% of the fatigue life. On the other hand, at the dynamic strain aging temperature, the operating temperature of nuclear pressure vessel, the variation of cyclic stress amplitude showed the primary and secondary hardening dependent on the strain rate and the total strain range. Dynamic strain aging was manifested as secondary hardening and a negative strain rate sensitivity by the maximum stress amplitude and micro-Vickers hardness. During the low cycle fatigue test at the dynamic strain aging regime in inert atmosphere, the variation of cyclic stress amplitude was nearly the same in air except for the occurrence of secondary hardening at the faster strain rate and the higher maximum strength. The earlier appearance of dynamic strain aging in inert atmosphere than in air may be caused by the reduced oxidation effect. Therefore, dynamic strain aging may be suppressed at the initial stage of deformation in air atmosphere. Dynamic strain aging in the oxidizing atmosphere enhanced the number of crack initiation sites by partitioning the local deformation but retarded the crack propagation rate by crack branching and by the suppressed plastic zone size. As the strain rate increased, the fatigue resistance increased at all temperatures. And the effect of dynamic strain aging on fatigue life in a smooth specimen was larger than oxidation effect, while the hardening by ...
Advisors
Kim, In-Sup김인섭
Description
한국과학기술원 : 원자력공학과,
Publisher
한국과학기술원
Issue Date
1995
Identifier
101881/325007 / 000895342
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력공학과, 1995.8, [ x, 112 p. ]

Keywords

Low Cycle Fatigue; Dynamic Strain Aging; Nuclear Pressure Vessel; 원자로압력용기; 저주파피로; 동적변형시효

URI
http://hdl.handle.net/10203/48848
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=101881&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
Files in This Item
There are no files associated with this item.

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0