• 제목/요약/키워드: martensitic steels

검색결과 88건 처리시간 0.027초

Corrosion Behaviors of Structural Materialsin High Temperature S-CO2 Environments

  • Lee, Ho Jung;Kim, Hyunmyung;Jang, Changheui
    • Corrosion Science and Technology
    • /
    • 제13권2호
    • /
    • pp.41-47
    • /
    • 2014
  • The isothermal corrosion tests of several types of stainless steels, Ni-based alloys, and ferritic-martensitic steels (FMS) were carried out at the temperature of 550 and $650^{\circ}C$ in SFR S-$CO_2$ environment (200 bar) for 1000 h. The weight gain was greater in the order of FMSs, stainless steels, and Ni-based alloys. For the FMSs (Fe-based with low Cr content), a thick outer Fe oxide, a middle (Fe,Cr)-rich oxide, and an inner (Cr,Fe)-rich oxide were formed. They showed significant weight gains at both 550 and $650^{\circ}C$. In the case of austenitic stainless steels (Fe-based) such as SS 316H and 316LN (18 wt.% Cr), the corrosion resistance was dependent on test temperatures except SS 310S (25 wt.% Cr). After corrosion test at $650^{\circ}C$, a large increase in weight gain was observed with the formation of outer thick Fe oxide and inner (Cr,Fe)-rich oxide. However, at $550^{\circ}C$, a thin Cr-rich oxide was mainly developed along with partially distributed small and nodular shaped Fe oxides. Meanwhile, for the Ni-based alloys (16-28 wt.% Cr), a very thin Cr-rich oxide was developed at both test temperatures. The superior corrosion resistance of high Cr or Ni-based alloys in the high temperature S-$CO_2$ environment was attributed to the formation of thin Cr-rich oxide on the surface of the materials.

상변태에 의한 잔류응력 완화효과에 관한 실험적 연구 (An Experimental Study on The Effect of Residual Stress Relaxation due to Phase Transformation)

  • 장경호;이진형;김재환
    • 대한용접접합학회:학술대회논문집
    • /
    • 대한용접접합학회 2003년도 추계학술발표대회 개요집
    • /
    • pp.216-218
    • /
    • 2003
  • Most of ferrous b.c.c weld materials may experience martensitic transformation during rapid cooling after welding. And it is well known that volume expansion due to phase transformation could influence in the case of welding of high tensile strength steels on the relaxation of welding residual stress. To apply this effect practically, it is a prerequisite to establish a numerical model which is able to estimate the effect of phase transformation on residual stress relaxation quantitatively. In this study, we investigated the effect of phase transformation on the relaxation of welding residual stress through experiment. And three-dimensional thermal elastic-plastic FEM analysis is conducted to compare the effect of phase transformation on the relaxation of welding residual stress in high strength steels(POSTEN60, POSTEN80) with analytical results which is not considering the effect of phase transformation on residual stress relaxation. According to the results, the extents of welding residual stress relaxation due to phase transformation in the case of welding of POSTEN60, POSTEN80 are 0.85 $\sigma$/$\sigma$$\sub$Y0/, 0.75$\sigma$/$\sigma$$\sub$Y0/, respectively.

  • PDF

화염경화 표면처리 공정에 의한 12Cr 강의 잔류응력 거동 (Behavior of the Residual Stress on the Surfaces of 12Cr Steels Generated by Flame Hardening Process)

  • 이민구;김광호;김경호;김흥회
    • 한국표면공학회지
    • /
    • 제37권4호
    • /
    • pp.226-233
    • /
    • 2004
  • The residual stresses on the surfaces of low carbon 12Cr steels used as a nuclear steam turbine blade material have been studied by controlling the flame hardening surface treatments. The temperature cycles on the surfaces of 12Cr steel were controlled precisely as a function of both the surface temperature and cooling rate. The final residual stress state generated by flame hardening was dominated by two opposite competitive contributions; one is tensile stress due to phase transformation and the other is compressive stress due to thermal contraction on cooling. The optimum processing temperatures required for the desirable residual stress and hardness were in the range of $850^{\circ}C$ to $960^{\circ}C$ on the basis of the specification of GE power engineering. It was also observed that the high residual tensile stress generated by flame hardening induced the cracks on the surfaces, especially across the prior austenite grain boundaries, and the material failure virtually, which might limit practical use of the surface engineered parts by flame hardening.

Development of Electrochemical Processes for Aluminium-Based Coatings for Fusion Applications

  • Konys, J.
    • Corrosion Science and Technology
    • /
    • 제15권6호
    • /
    • pp.314-319
    • /
    • 2016
  • Reduced activation ferritic-martensitic steels (RAFM) are envisaged in future fusion technology as structural material which will be in direct contact with a flowing liquid lead-lithium melt, serving as breeder material. Aluminium-based coatings had proven their ability to protect the structural material from corrosion attack in flowing Pb-15.7Li and to reduce tritium permeation into the coolant, significantly. Coming from scales produced by hot dipping aluminization (HDA), the development of electrochemical-based processes to produce well-defined aluminium-based coatings on RAFM steels gained increased attention in research during the last years. Two different electrochemical processes are described in this paper: The first one, referred to as ECA, is based on the electrodeposition of aluminium from volatile, metal-organic electrolytes. The other process called ECX is based on ionic liquids. All three processes exhibit specific characteristics, for example in the field of processability, control of coating thicknesses (low activation criteria) and heat treatment behavior. The aim of this article is to compare these different coating processes critically, whereby the focus is on the comparison of ECA and ECX processes. New results for ECX will be presented and occurring development needs for the future will be discussed.

Simulation of impact toughness with the effect of temperature and irradiation in steels

  • Wang, Chenchong;Wang, Jinliang;Li, Yuhao;Zhang, Chi;Xu, Wei
    • Nuclear Engineering and Technology
    • /
    • 제51권1호
    • /
    • pp.221-227
    • /
    • 2019
  • One of the important requirements for the application of reduced activation ferritic/martensitic steel is to retain proper mechanical properties in irradiation and high temperature conditions. In order to simulate the impact toughness with the effect of temperature and irradiation, a simulation model based on energy balance method consisted of crack initiation, plastic propagation and cleavage propagation stages was established. The effect of temperature on impact toughness was analyzed by the model and the trend of the simulation results was basicly consistent with the previous experimental results of CLAM steels. The load-displacement curve was simulated to express the low temperature ductile-brittle transition. The effect of grain size and inclusion was analyzed by the model, which was consistent with classical experiment results. The transgranular-intergranular transformation in brittle materials was also simulated.

Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa

  • Ji Ho Shin ;Byeong Seo Kong;Chaewon Jeong;Hyun Joon Eom;Changheui Jang;Lin Shao
    • Nuclear Engineering and Technology
    • /
    • 제55권2호
    • /
    • pp.555-565
    • /
    • 2023
  • Despite many advantages as structural materials, austenitic stainless steels (SSs) have been avoided in many next generation nuclear systems due to poor void swelling resistance. In this paper, we report the results of heavy ion irradiation to the recently developed advanced radiation resistant austenitic SS (ARES-6P) with nanosized NbC precipitates. Heavy ion irradiation was performed at high temperatures (500 ℃ and 575 ℃) to the damage level of ~200 displacement per atom (dpa). The measured void swelling of ARES-6P was 2-3%, which was considerably less compared to commercial 316 SS and comparable to ferritic martensitic steels. In addition, increment of hardness measured by nano-indentation was much smaller for ARES-6P compared to 316 SS. Though some nanosized NbC precipitates were dissociated under relatively high dose rate (~5.0 × 10-4 dpa/s), sufficient number of NbC precipitates remained to act as sink sites for the point defects, resulting in such superior radiation resistance.

고강도강(POSTEN60, POSTEN80) 용접접합부의 잔류응력 (Residual Stress in Welds of High Strength Steel( POSTEN60, POSTEN80))

  • 장경호;이진형
    • 한국강구조학회 논문집
    • /
    • 제16권5호통권72호
    • /
    • pp.519-528
    • /
    • 2004
  • 대부분의 용접재는 용접 후 빠른 속도로 냉각하는 과정에서 재료조직의 변화, 즉 상변태(마르텐사이트변태)가 일어난다. 그리고 이러한 상변태에 의한 체적의 팽창은 특히 고강도강재의 용접시 용접부의 잔류응력완화에 기여한다. 따라서 고강도강을 적용한 강구조물 접합부의 잔류응력 특징을 파악하기 위해서는 고강도강 용접시 상변태가 잔류응력완화에 미치는 효과를 정량적으로 평가할 수 있는 수치적 모델을 확립해야 한다. 본 연구에서는 고강도강 용접시 상변태에 의한 체적의 팽창이 잔류응력 완화에 미치는 영향을 잔류응력 측정 실험을 통하여 조사하였고, 이를 바탕으로 상변태에 의한 잔류응력완화를 고려한 고강도강 및 이종강재 용접접합부의 잔류응력 특징을 3차원 열탄소성 해석기법 개발을 통하여 재현하였다.

압력용기용 Ni-Mo-Cr계 고강도 저합금강의 합금원소 함량 변화에 따른 미세조직학적 특성변화의 열역학 계산 및 평가 (Thermodynamic Calculation and Observation of Microstructural Change in Ni-Mo-Cr High Strength Low Alloy RPV Steels with Alloying Elements)

  • 박상규;김민철;이봉상;위당문
    • 대한금속재료학회지
    • /
    • 제46권12호
    • /
    • pp.771-779
    • /
    • 2008
  • An effective way of increasing the strength and fracture toughness of reactor pressure vessel steels is to change the material specification from that of Mn-Mo-Ni low alloy steel(SA508 Gr.3) to Ni-Mo-Cr low alloy steel(SA508 Gr.4N). In this study, we evaluate the effects of alloying elements on the microstructural characteristics of Ni-Mo-Cr low alloy steel. The changes in the stable phase of the SA508 Gr.4N low alloy steel with alloying elements were evaluated by means of a thermodynamic calculation conducted with the software ThermoCalc. The changes were then compared with the observed microstructural results. The calculation of Ni-Mo-Cr low alloy steels confirms that the ferrite formation temperature decreases as the Ni content increases because of the austenite stabilization effect. Consequently, in the microscopic observation, the lath martensitic structure becomes finer as the Ni content increases. However, Ni does not affect the carbide phases such as $M_{23}C_6 $ and $M_7C_3$. When the Cr content decreases, the carbide phases become unstable and carbide coarsening can be observed. With an increase in the Mo content, the $M_2C$ phase becomes stable instead of the $M_7C_3$ phase. This behavior is also observed in TEM. From the calculation results and the observation results of the microstructure, the thermodynamic calculation can be used to predict the precipitation behavior.

FUSION MATERIALS AND FUSION ENGINEERING R&D IN JAPAN

  • KOHYAMA A.;KONISHI S.;KIMURA A.
    • Nuclear Engineering and Technology
    • /
    • 제37권5호
    • /
    • pp.423-432
    • /
    • 2005
  • Japanese activities on fusion structural materials R&D have been well organized under the coordination of university programs and JAERI/NIMS programs more than two decades. Where, two categories of structural materials have been studied, those are; reduced activation martensitic/ferritic steels (RAFs) as reference material and vanadium alloys and SiC/SiC composite materials as advanced materials. The R&D histories of these candidate materials and the present status in Japan are reviewed with the emphasis on materials behavior under radiation damage. The importance of IFMIF and technology development for blanket R&D including ITER-TBRG activity is emphasized and the current status of those activities in Japan is also presented.

저주기 피로부하에서 F82H 강 TIG 용접 접합부의 피로손상거동 (Fatigue Damage Behavior in TIG Welded Joint of F82H Steel under Low Cycle Fatigue Loading)

  • 김동현;박기원
    • Journal of Welding and Joining
    • /
    • 제33권6호
    • /
    • pp.42-48
    • /
    • 2015
  • Reduced activation ferritic/martensitic steels are recognized as the primary candidate structural materials for fusion blanket systems. Welding is an inevitable for breeding blanket for pressure tightness and radioisotope confinement. Especially, TIG welding was chosen for sealing because it has the largest gap allowance compared to the other welding methods, and its properties are controllable by feed wire and welding conditions. In this study, the low cycle fatigue test using two-type gage such as extensometer and strain gage was applied to the TIG welded joint of F82H steel, for evaluating fatigue damage accumulation behavior of the HAZs. As the result, the over-tempered HAZ have shown a higher fatigue damage accumulation compared with other materials at all the testing conditions.