• Title/Summary/Keyword: SA312 TP316 Stainless Steel

Search Result 5, Processing Time 0.017 seconds

Effect of Loading Rate on the Deformation Behavior of SA508 Gr.1a Low Alloy Steel and TP316 Stainless Steel Pipe Materials at RT and 316℃ (상온과 316℃에서 SA508 Gr.1a 저합금강 배관과 TP316 스테인리스강 배관의 변형거동에 미치는 하중속도의 영향)

  • Kim, Jin Weon;Choi, Myung Rak
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.39 no.4
    • /
    • pp.383-390
    • /
    • 2015
  • This study conducted tensile tests on SA508 Gr.1a low alloy steel and SA312 TP316 stainless steel piping materials under various strain rates at room temperature (RT) and $316^{\circ}C$ to investigate the effects of loading rate on the deformation behavior of nuclear piping materials. At RT, the deformation behavior for both pipe materials showed a typical loading rate dependence, i.e., the strength increased and the ductility decreased as the loading rate increased. At $316^{\circ}C$, however, the strength and elongation of SA508 Gr.1a low alloy steel decreased as the loading rate increased, and its reduction of area non-linearly varied with the loading rate. For SA312 TP316 stainless steel, the strength, elongation, and reduction of area at $316^{\circ}C$ were almost the same regardless of the loading rate. At both temperatures, the strain hardening capacity was nearly independent of the loading rate for SA508 Gr.1a low alloy steel, while it decreased with increasing loading rate for SA312 TP316 stainless steel.

Effect of Loading Rate on the Fracture Behavior of Nuclear Piping Materials Under Cyclic Loading Conditions

  • Kim, Jin Weon;Choi, Myung Rak;Kim, Yun Jae
    • Nuclear Engineering and Technology
    • /
    • v.48 no.6
    • /
    • pp.1376-1386
    • /
    • 2016
  • This study investigated the loading rate effect on the fracture resistance under cyclic loading conditions to understand clearly the fracture behavior of piping materials under seismic conditions. J-R fracture toughness tests were conducted under monotonic and cyclic loading conditions at various displacement rates at room temperature and the operating temperature of nuclear power plants (i.e., $316^{\circ}C$). SA508 Gr.1a low-alloy steel and SA312 TP316 stainless steel piping materials were used for the tests. The fracture resistance under a reversible cyclic load was considerably lower than that under monotonic load regardless of test temperature, material, and loading rate. Under both cyclic and monotonic loading conditions, the fracture behavior of SA312 TP316 stainless steel was independent of the loading rate at both room temperature and $316^{\circ}C$. For SA508 Gr.1a lowalloy steel, the loading rate effect on the fracture behavior was appreciable at $316^{\circ}C$ under cyclic and monotonic loading conditions. However, the loading rate effect diminished when the cyclic load ratio of the load (R) was -1. Thus, it was recognized that the fracture behavior of piping materials, including seismic loading characteristics, can be evaluated when tested under a cyclic load of R = -1 at a quasistatic loading rate.

Evaluation of Deformation Behavior of Nuclear Structural Materials under Cyclic Loading Conditions via Cyclic Stress-Strain Test (반복 응력-변형률 시험을 통한 반복하중 조건에서 원전 주요 구조재료의 변형거동 평가)

  • Kim, Jin Weon;Kim, Jong Sung;Kweon, Hyeong Do
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.13 no.1
    • /
    • pp.75-83
    • /
    • 2017
  • This study investigated deformation behavior of major nuclear structural materials under cyclic loading conditions via cyclic stress-strain test. The cyclic stress-strain tests were conducted on SA312 TP316 stainless steel and SA508 Gr.3 Cl.1 low-alloy steel, which are used as materials for primary piping and reactor pressure vessel nozzle respectively, under cyclic load with constant strain amplitude and constant load amplitude at room temperature (RT) and $316^{\circ}C$. From the results of tests, the cyclic hardening and softening behavior, stabilized cyclic stress-strain behavior, and ratcheting behavior of both materials were investigated at both RT and $316^{\circ}C$. In addition, appropriate considerations for cyclic deformation behavior in the structural integrity evaluation of major nuclear components under excessive seismic condition were discussed.

Effect of Induction Heat Bending Process on the Corrosion Properties of 316 Stainless Steel Pipes for Nuclear Power Plant (원자력발전소용 316 스테인리스강 배관의 부식특성에 미치는 유도가열벤딩공정의 영향)

  • Shin, Mincheol;Kim, Young Sik;Kim, Kyungsu;Chang, Hyunyoung;Park, Heungbae;Sung, Giho
    • Corrosion Science and Technology
    • /
    • v.13 no.3
    • /
    • pp.87-94
    • /
    • 2014
  • Recently, the application of bending products has been increased since the industries such as automobile, aerospace, ships, and plants greatly need the usage of pipes. For facility fabrication, bending process is one of key technologies for pipings. Induction heat bending process is composed of bending deformation by repeated local heat and cooling. Because of local heating and compressive strain, detrimental phases may be precipitated and microstructural change can be induced. This work focused on the effect of induction heat bending process on the properties of ASME SA312 TP316 stainless steel. Evaluation was done on the base metal and the bended areas before and after heat treatment. Microstructure analysis, intergranular corrosion test including Huey test, double loop electropotentiokinetic reactivation test, oxalic acid etch test, and anodic polarization test were performed. On the base of microstructural analysis, grain boundaries in bended extrados area were zagged by bending process, but there were no precipitates in grain and grain boundary and the intergranular corrosion rate was similar to that of base metal. However, pitting potentials of bended area were lower than that of the base metal and zagged boundaries was one of the pitting initiation sites. By re-annealing treatment, grain boundary was recovered and pitting potential was similar to that of the base metal.

Evaluation of Material Properties for Yonggwang Nuclear Piping System(I)-Shutdown Cooling System- (영광원자력 배관소재의 재료물성치 평가 (1)-정지냉각계통-)

  • 석창성;최용식;장윤석;김종욱
    • Transactions of the Korean Society of Mechanical Engineers
    • /
    • v.18 no.5
    • /
    • pp.1106-1116
    • /
    • 1994
  • Leak Before Break(LBB) design concept is applied to piping systems of newly-built Yonggwang 3, 4 nuclear generating stations as a design alternative to the provision of pipe whip restraints, in recognition of the questionable benefits of providing such restraints. The objective of this paper is to evaluate the material properties (tensile and fracture toughness) of SA312 TP316 stainless steel and their associated welds manufactured for shutdown cooling system of Yonggwang 3, 4 nuclear generating stations. Effect of various parameters such as specimen orientation, test temperature, welding on material properties were examined.