• Title/Summary/Keyword: 316 Stainless Steel

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A Study for Experiment to Measure Mechanical Properties of Pressurizer Nozzle and Safety-Ends in Nuclear Power Plant (원전 가압기 노즐 및 안전단 재료에 대한 기계적 물성시험 연구)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Kim, Jin-Weon
    • Journal of the Korean Society for Nondestructive Testing
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    • v.33 no.2
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    • pp.147-153
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    • 2013
  • Recently the primary water stress corrosion cracking(PWSCC) has occurred in the dissimilar metal weld region between pressurizer nozzle and safe-end in nuclear power plants(NPPs). As material of the pressurizer nozzle, SA508 Gr. 3 low alloy steel was used. F316L stainless steel and Alloy 82/182 were used as safe-end and weld metal, respectively. Although mechanical properties are needed for evaluation of the structural integrity against flaw in the material, material specification and standard don't supply those properties. Therefore, the present study conducted tensile and fracture toughness tests on SA508 Gr.3 and F316L stainless steel at ambient temperature and operating temperature of NPPs and reported the tested results.

Study of Practical Cathodic Protection of 2nd Class Stainless Steel Shaft by means of Al Sacrificial Anode (AL계 희생양극에 의한 2종스테인리스 강축의 음극방식 실용화 연구)

  • Son, Yeong-Tae;Lee, Myeong-Hun;Lee, Hui-Jun
    • Journal of Korea Ship Safrty Technology Authority
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    • s.22
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    • pp.34-53
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    • 2007
  • In the case of hull material. large sized merchant ships are made of steel, on the other hand FRP or wood are used for small sized fishing boats. At present in Korea approximately 88,500 fishing boats are in operation of which 70% are made of FRP In the meantime, stainless steel is frequently used as shaft materials of the small-size FRP fishing boat. Namely, the kinds of shaft materials are STS 304(18Cr-8Ni), STS 316(18Cr-12Ni-2.5Mo steel) and STS 630(17Cr-Ni-Nb steel)etc. Among these things, STS 304 which is the cheapest and having ordinary corrosion resistance is most widely used as 2nd class shaft material. But, using STS 304 for shaft system material of the small-size FRP fishing boat on seawater environments entails a severe corrosion which causes shaft system troubles. Particularly, the corrosions tend to be concentrated of the stern and bow side, propeller shaft surface of inside of stern tube and the boat having no stern cooling pipe line system. As a solution for those problems, research on the ways to mitigate corrosion on the part of 2nd class stainless steel shaft have been undertaken. In the result, not only clarification for the reason of corrosion of the part of stainless steel shaft used mainly for the small-size FRP fishing boat was done, but also most optimal corrosion protection system was developed by experimenting shaft's protection simulation based of the electrochemical cathodic protection principle. In addition, verification through the field test on the optimal cathodic corrosion protection method by means of aluminum sacrificial anode was carried out. In this study, effective and economical shaft's protection system is suggested to the small-size FRP fishing boat operator by substantiating the results obtained from the research on the optimal cathodic protection.

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CORROSION BEHAVIOR OF AUSTENITIC AND FERRITIC STEELS IN SUPERCRITICAL WATER

  • Luo, Xin;Tang, Rui;Long, Chongsheng;Miao, Zhi;Peng, Qian;Li, Cong
    • Nuclear Engineering and Technology
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    • v.40 no.2
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    • pp.147-154
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    • 2008
  • The general corrosion behavior of austenitic and ferritic steels(316L, 304, N controlled 304L, and 410) in supercritical water is investigated in this paper. After exposure to deaerated supercritical water at $480^{\circ}C$/25 MPa for up to 500 h, the four steels studied were characterized using gravimetry, scanning electron microscopy/energy dispersive X-ray spectroscopy(SEM/EDS), X-ray photoelectron spectroscopy(XPS), and X-ray diffraction(XRD). The results show that the 316L steel with a higher Cr and Ni content has the best corrosion-resistance performance among the steels tested. In addition to the oxide layer mixed with $Fe_{3}O_{4}$ and $(Fe,Cr)_{3}O_{4}$ that formed on all the samples, a $Fe_{3}O_{4}$ loose outer layer was observed on the 410 steel. The corrosion mechanism of stainless steels in supercritical water is discussed based on the above results.

The low temperature plasma nitrocarburizng of AISI304L and AISI316L stainless steel (AISI304L과 AISI316L강의 저온프라즈마 질탄화 처리 )

  • Jeong, Gwang-Ho;Lee, In-Seop
    • Proceedings of the Korean Institute of Surface Engineering Conference
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    • 2007.11a
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    • pp.153-154
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    • 2007
  • AISI316L강은 AISI304L강과 기본 조성은 같지만 316L강이 약 2.5%의 Mo가 첨가되어 있다. 저온 플라즈마 질탄화 시 모재에 첨가된 Mo의 영향을 조사하기 위하여 처리온도를 변화시켜 실험하였다. 같은 처리온도의 경우 경화층의 두께는 316L강이 비교적 두껍게 형성되었다. 316L강의 경우 $450^{\circ}C$이하에서 약 25 ${\mu}m$까지 형성되었고, 306L강의 경우 $400^{\circ}C$에서 약 10 ${\mu}m$까지 형성되었다. $400^{\circ}C$ 이하에서 경화층은 두 가지시편 모두 확장된 오스테나이트 (${\gamma}_N,\;{\gamma}_c$)로 이루어져 있으나, 304L의 경우 $430^{\circ}C$부터 석출물(CrN)이 형성되기 시작하였다. 316L의 경우 $450^{\circ}C$까지 석출물이 형성되지 않았고, $480^{\circ}C$에서 석출물 (CrN)이 관찰되었다. 석출물이 형성된 시편을 제외한 모든 시편의 내식성은 모제보다 증가 하였다.

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Qualitative Analysis of the Component Materials of Nuclear Power Plant Using Time-Resolved Laser Induced Breakdown Spectroscopy (시간분해 레이저 유도 파열 분광분석에 의한 원자력발전소 계통재질의 성분 정성분석)

  • Chung, Kun-Ho;Cho, Yeong-Hyun;Lee, Wanno;Choi, Geun-Sik;Lee, Chang-Woo
    • Analytical Science and Technology
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    • v.17 no.5
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    • pp.416-422
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    • 2004
  • Time-resolved laser induced breakdown spectroscopy (TRELIBS) has been developed and applied to the qualitative analysis of the component materials of nuclear power plant. The alloy samples used in this work were carbon steels (A106 Gr. B; A336 P11; A335 P22), stainless steels (type 304; type 316) and inconel alloys (Inconel 600; Inconel 690; Inconel 800). Carbon steels can be individually distinguished by the intensity ratio of chromium to iron and molybdenum to iron emission lines observed at the wavelength raging from 485 to 575 nm. Type 316 stainless steel can be easily differentiated from type 304 by identification of the molybdenum emission lines at an emission wavelength ranging from 485 to 575 nm: type 304 does not give any molybdenum emission lines, but type 316 does. The inconel alloys can be individually distinguished by the intensity ratio of Cr/Fe and Ni/Fe emission lines at the wavelength raging from 420 to 510 nm. TRELIBS has been proved to be a powerful analytical technique for direct analysis of alloys due to its non-destructivity and simplicity.

The effect of sigma phases formation depending on Cr/Ni equivalent ratio in AISI 316L austenitic stainless steel weldments. (AISI 316L 용접부의 시그마상 형성에 영향을 미치는 크롬/니켈 당량비)

  • Kim, Y.H.;Jang, A.Y.;Choi, C.H.;Kang, D.H.;Jeon, J.H.;Byun, J.C.;Jung, G.H.;Lee, S.H.;Lee, H.W.
    • Proceedings of the KWS Conference
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    • 2010.05a
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    • pp.21-21
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    • 2010
  • AISI 316L 용접금속의 크롬/니켈 당량비에 따른 시그마상의 영향을 알아보기 위하여 응고모드가 다른 3종류의 플럭스 코어드 와이어를 제작하였다. AISI 316L 시편에 FCAW 프로세스를 적용한 용접재를 $650^{\circ}C$, $750^{\circ}C$, $850^{\circ}C$, $950^{\circ}C$에서 각 각 1H, 5H, 24H, 72H동안 열처리하였다. 크롬/니켈 당량비가 높을수록 즉, 크롬의 함량이 높아질수록 $\delta$-페라이트 함량은 증가하였으며, $\delta$-페라이트는 고온에서 시그마상으로 변태되었다. $\delta$-페라이트는 $650^{\circ}C$에서 가장 느리게 분해되었으며 $850^{\circ}C$에서 가장 활발히 분해되었다. 용접부의 특성상 크롬과 니켈 등의 합금원소에 의하여 응고온도범위가 넓어져 $950^{\circ}C$에서도 시그마상이 석출되었으며, 5시간 이상 유지 시 구형으로 존재하였다. 충격시험 시 시그마상에 의해 취약해진 inter-dendrite 를 따라 파면이 형성되었으며, $-100^{\circ}C$이하의 극저온에서는 시그마상의 양과 무관하게 충격흡수에너지는 0에 가까워졌다. 하지만 3%미만의 $\delta$-페라이트를 함유하는 AF모드에서 발생한 DDC와 미량의 시그마상은 충격흡수에너지에 결정적인 영향을 미치지 않았다.

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A Study on Thermal Ratcheting Structure Test of 316L Test Cylinder (316L 시험원통의 열라체팅 구조시험에 관한 연구)

  • Lee, H.Y.;Kim, J.B.;Koo, G.H.
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.243-249
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    • 2001
  • In this study, the progressive inelastic deformation, so called, thermal ratchet phenomenon which can occur in high temperature liquid metal reactor was simulated with thermal ratchet structural test facility and 316L stainless steel test cylinder. The inelastic deformation of the reactor baffle cylinder can occur due to the moving temperature distribution along the axial direction as the hot free surface moves up and down under the cyclic heat-up and cool-down of reactor operations. The ratchet deformations were measured with the laser displacement sensor and LVDTs after cooling the structural specimen which experiences thermal load up to $550^{\circ}$ and the temperature differences of about $500^{\circ}C$. During structural thermal ratchet test, the temperature distribution of the test cylinder along the axial direction was measured from 28 channels of thermocouples and the temperatures were used for the ratchet analysis. The thermal ratchet deformation analysis was performed with the NONSTA code whose constitutive model is nonlinear combined kinematic and isotropic hardening model and the test results were compared with those of the analysis. Thermal ratchet test was carried out with respect to 9 cycles of thermal loading and the maximum residual displacements were measured to be 1.8mm. It was shown that thermal ratchet load can cause a progressive deformation to the reactor structure. The analysis results with the combined hardening model were in reasonable agreement with those of the tests.

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Microstructural Analysis of STS316L Samples Manufactured by Powder Bed Fusion and Post-heat Treatments (Powder Bed Fusion 공정으로 제조한 STS 316L의 미세조직과 후속 열처리 특성)

  • Song, S.Y.;Lee, D.W.;Cong, D.V.;Kim, J.W.;Lee, S.M.;Joo, S.H.;Kim, Jin-Chun
    • Journal of Powder Materials
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    • v.29 no.1
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    • pp.14-21
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    • 2022
  • In the powder bed fusion (PBF) process, a 3D shape is formed by the continuous stacking of very fine powder layers using computer-aided design (CAD) modeling data, following which laser irradiation can be used to fuse the layers forming the desired product. In this method, the main process parameters for manufacturing the desired 3D products are laser power, laser speed, powder form, powder size, laminated thickness, and laser diameter. Stainless steel (STS) 316L exhibits excellent strength at high temperatures, and is also corrosion resistant. Due to this, it is widely used in various additive manufacturing processes, and in the production of corrosion-resistant components with complicated shapes. In this study, rectangular specimens have been manufactured using STS 316L powder via the PBF process. Further, the effect of heat treatment at 800 ℃ on the microstructure and hardness has been investigated.

Effects of Solidification Modes on the Pit Initiation and Propagation in Austenitic Stainless Steel Weld Metals (오스테나이트계 스테인리스강 용착금속의 응고모드가 공식 생성 및 성장에 미치는 영향 x Effects of Solidification Modes on the Pit Initiation and Propagation in Austenitic Stainless Steel Weld Metals)

  • 최한신;김규영;이창희
    • Journal of Welding and Joining
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    • v.16 no.6
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    • pp.59-68
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    • 1998
  • In this study, effects of solidification modes (primary $\delta$-ferrite, primary ${\gamma}$-austenite) on the pit initiation and propagation in the 304L and 316L austenitic stainless steel weld metals were investigated. The solidification mode of weld metal was controlled by the addition of nitrogen to Ar shielding gas. Through the electrochemical experiments (potentiodynamic anodic polarization and potentiostatic time-current transient test) and metallographic examination (microstructure and elemental distribution), the following results were obtained. The more the volume content of nitrogen in the shielding gas were, the lower critical current density for passivity was observed. In comparison with weldments solidified through the primary $\delta$-ferrite solidification mode and the primary ${\gamma}$-solidification mode, the former showed higher critical pitting potential and a longer incubation time for stable pit initiation than the latter. However, in the pit propagation stage the former exhibited a faster dissolution rate than the latter. These results were believed to ee related to the distribution of alloying elements such as Cr, Mo, Ni and S.

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Optimal Electropolishing Condition of Austenitic Stainless Steel Specimens for Slow Strain Rate Tensile Testing (오스테나이트 스테인리스강 저속인장시험편의 최적 전해연마 특성)

  • Min-Jae Choi;Eun-Byeoul Jo;Dong-Jin Kim
    • Corrosion Science and Technology
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    • v.22 no.6
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    • pp.457-465
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    • 2023
  • Irradiation-assisted stress corrosion cracking (IASCC) is one of the main degradation mechanisms of austenitic stainless steels, which are used as reactor internal materials. Slow strain rate testing (SSRT) has been widely applied to evaluate the IASCC initiation characteristics of proton-irradiated tensile specimens. Tensile specimens require low surface roughness for micro-crack observation, and electropolishing is the most important specimen pre-treatment process used for this. In this study, optimal electropolishing conditions were examined through analyzing results of polarization experiments and surface roughness measurements after electropolishing. Corrosion cell and electropolishing equipment were fabricated for polarization tests and electropolishing experiments using SSRT specimens. The experimental parameters were electropolishing time, current density, electrolyte temperature, and stirring speed. The optimal electropolishing conditions for SSRT tensile specimens made of type 316 stainless steel were evaluated as a polishing time of 180 seconds, a current density of 0.15 A/cm2, an electrolyte temperature of 60 ℃, and a stirring speed of 200 RPM.