• 제목/요약/키워드: Iron chromium alloy

검색결과 22건 처리시간 0.026초

자동차 머플러의 스테인리스 강판 성형기술에 관한 연구 (Forming Technology of Stainless Steel Sheet for Automotive Muffler Part)

  • 박동환;소범식;배원락;조용;김태준;고태조
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2008년도 추계학술대회 논문집
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    • pp.230-233
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    • 2008
  • Stainless steels are alloy steels with iron as the primary constituent and chromium, nickel, and manganese as principal alloying elements. In addition to automotive, construction, and transportation industries, stainless steels have a variety of applications in the food, chemical, and pharmaceutical industries. Some common products made from stainless steel are sinks, wash basins, kitchen vessels, and cutlery. Among ferritic stainless steels, type 409 can be cold-formed easily and are used for deep-drawn parts such as vessels for the chemical and food industries. In this study, forming analyses and experiments to prevent the occurrence of inferiority such as wrinkles, crack, and neck for automotive muffler part are carried out to save the optimal conditions during forming by modifying the blank size and shape, blank holding force etc.

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복합 크롬 분말에 의한 철계 용접 오버레이의 내마모 특성 (Wear Resistance Characteristics of Iron Weld Overlays by Composite Chromium Powders)

  • 김종철;박경채;최창옥
    • Journal of Welding and Joining
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    • 제19권5호
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    • pp.506-511
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    • 2001
  • Weld overlay has been developed to improve the property of material surface which is used in the severe environment. Weld overlay is the process which uses an arc heat and welds different composition of alloy on the substrate for the improvements of heat resistance and wear resistance. Weld overlay has a lot of advantages which are high hardness, good processing efficiency, easy controlling of layer thickness, good quality and low cost. In this study, weld overlay was performed by MAG welding on the base metal(SS400) with filler metal which contain composite powders(Cr+C+Mn+Mo+NbC) and solid wire(JIS-YGW11). Characterization of hardness and wear resistance were analyzed by EDS, EPMA, XRD and observations of microstructure were performed to investigate characteristics of overlays. The experimental results of overlaid specimens manufactured with Cr+C+Mn+Mo+NbC powders were obtained as fellows. ${\alpha}-phase$, M(Fe, Cr)3C and NbC of overlays were increased with decreasing the wire feed rates and increasing powder feed rates. Also the hardness of overlays were increased and the specific wear were decreased.

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Cr 및 Nb 복합탄화물에 의한 철계 MAG용접 오버fp이의 내마모 특성 (Wear Resistance Characteristics of Iron System MAG Weld Overlays with Chromium and Niobium Carbide Composite)

  • 김종철;박경채
    • Journal of Welding and Joining
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    • 제20권3호
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    • pp.54-59
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    • 2002
  • Overlays is a treatment of the surface and near-surface regions of a material to allow the surface to perform functions that are distinct from those frictions demanded far the bulk of the material. Welding, thermal spray, quenching, carburizing and nitration have been used as the surface treatment. Especially, weld overlay is a relatively thick layer of filler metal applied to a carbon or low-alloy steel base metal for the purpose of providing a wear resistant surface. In this study, weld overlay was performed by MAG welding on the base metal(SS400) with filler metal which contain composite powders($Cr_3C_2+Mn+Mo+NbC$) and solid wire(JIS-YGW11). Characteristics of hardness and wear resistance on overlays were analyzed by EDS, EPMA, XRD and microstructures. Carbide formations were $M(Cr, Fe)_7C_3$ and NbC phases. And carbide volume fraction, hardness and specific wear resistance of overlays were increased with increasing powder feed rate and decreasing wire fred rate. Hardness and wear resistance were almost proportioned to carbide volume fraction of overlay.

화력발전소의 장수명화를 위한 Cr 강(鋼)의 고온 $SO_2$가스 부식저감 대책 기술 (Corrosion Prevention of Cr steels in $SO_2$ Atmosphere for Electrial Power Plants)

  • 이동복;최정호
    • 한국표면공학회:학술대회논문집
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    • 한국표면공학회 2007년도 춘계학술발표회 초록집
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    • pp.114-115
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    • 2007
  • The corrosion characteristics of Cr steels were investigated to protect Cr steels from the SO2-gas corrosion in the coal-fired power plant. The samples tested were low alloy ferritic steel (ASTM T22, 23), martensitic steel (ASTM T91, 92, 122), and austenitic stainless steel (ASTM 347HFG). The corrosion tests were performed between 600oC and 1000oC in Ar + (0.2, 1)%SO2 gas for 100 hr. Chromium was quite beneficial to corrosion resistance, while iron was not. The corrosion resistance increased in the order of T22, T23, T91, T92, T122, and 347HFG.

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크롬백주철의 기지조직 및 탄화물에 있어서 합금원소의 거동 (The Distribution Behavior of Alloying Elements in Matrices and Carbides of Chromium White Cast Iron)

  • 류성곤
    • 한국재료학회지
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    • 제10권7호
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    • pp.489-492
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    • 2000
  • 0.5%C-25.0%Cr-1.0%Si(합금1), 0.5%C-5.0%Cr-1.0%Si(합금2) 및 2.0%C-5.0%Cr-1.0%Si(합금3)의 3종류 크롬백주철에 있어서 기지조직 및 탄화물에 분푀도는 Cr 및 Si의 거동을 연구하였다. 15kg 용량의 고주파 유도용해로에 선철, 고철, Fe-Cr, Fe-Si 등을 장입시켜 용해시킨후 슬래그를 제거시키고 $1550^{\circ}C$에서 펩 주형에 주입시킨후 실온까지 냉각시켜 SEM으로 응고조직을 관찰하였으며 EPMA분석을 통하여 Cr 및 Si 의 분포거동을 관찰하였다. 합금1의 경우 초정으로 $\delta$페라이트가 정출후 $\delta$페라이트와 용액의 입계에서 $\delta$페라이트와 $M_7C_3$탄화물이 공정으로 정출하였으며 합금2의 경우 용액에서 초정으로 거의 $\delta$페라이트가 정출된 수 극히 일부분만이 $\delta$페라이트와 $M_7C_3$탄화물의 공정으로 정출하였다. 반면 합금 3의 경우 오스테나이트가 초정으로 정출된 후 오스테나이트와 $M_3C$탄화물이 공정으로 정출하였다. Cr은 주로 $M_7C_3$$M_3C$탄화물에 , 그리고 Si는 기지조직에 선택적으로 분배되었으며 Cr의 기지조직에 대한 분배계수는 0.56-0.68, 그리고 Si는 1.12-1.28의 범위에 걸쳐있었다. 또한 Cr의 기지조직에 대한 분배계수는 C 함량이 2.0%일때가 0.5%의 경우보다 낮았으며 $M_7C_3$탄화물내의 Cr 함량은 Cr함량이 25.0% 일때가 5.0%의 경우보다 높은값을 나타내었다. 나타내었다.

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Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

  • Cheng, Bo;Kim, Young-Jin;Chou, Peter
    • Nuclear Engineering and Technology
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    • 제48권1호
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    • pp.16-25
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    • 2016
  • In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconiumalloy fuel claddingmaterials are rapidlyheateddue to nuclear decay heating and rapid exothermic oxidation of zirconium with steam. This heating causes the cladding to rapidly react with steam, lose strength, burst or collapse, and generate large quantities of hydrogen gas. Although maintaining core cooling remains the highest priority in accident management, an accident tolerant fuel (ATF) design may extend coping and recovery time for operators to restore emergency power, and cooling, and achieve safe shutdown. An ATF is required to possess high resistance to steam oxidation to reduce hydrogen generation and sufficient mechanical strength to maintain fuel rod integrity and core coolability. The initiative undertaken by Electric Power Research Institute (EPRI) is to demonstrate the feasibility of developing an ATF cladding with capability to maintain its integrity in $1,200-1,500^{\circ}C$ steam for at least 24 hours. This ATF cladding utilizes thin-walled Mo-alloys coated with oxidation-resistant surface layers. The basic design consists of a thin-walled Mo alloy structural tube with a metallurgically bonded, oxidation-resistant outer layer. Two options are being investigated: a commercially available iron, chromium, and aluminum alloy with excellent high temperature oxidation resistance, and a Zr alloy with demonstratedcorrosionresistance.Asthese composite claddings will incorporate either no Zr, or thin Zr outer layers, hydrogen generation under severe LOCA conditions will be greatly reduced. Key technical challenges and uncertainties specific to Moalloy fuel cladding include: economic core design, industrial scale fabricability, radiation embrittlement, and corrosion and oxidation resistance during normal operation, transients, and severe accidents. Progress in each aspect has been made and key results are discussed in this document. In addition to assisting plants in meeting Light Water Reactor (LWR) challenges, accident-tolerant Mo-based cladding technologies are expected to be applicable for use in high-temperature helium and molten salt reactor designs, as well as nonnuclear high temperature applications.

High alloyed new stainless steel shielding material for gamma and fast neutron radiation

  • Aygun, Bunyamin
    • Nuclear Engineering and Technology
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    • 제52권3호
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    • pp.647-653
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    • 2020
  • Stainless steel is used commonly in nuclear applications for shielding radiation, so in this study, three different types of new stainless steel samples were designed and developed. New stainless steel compound ratios were determined by using Monte Carlo Simulation program Geant 4 code. In the sample production, iron (Fe), nickel (Ni), chromium (Cr), silicium (Si), sulphur (S), carbon (C), molybdenum (Mo), manganese (Mn), wolfram (W), rhenium (Re), titanium (Ti) and vanadium (V), powder materials were used with powder metallurgy method. Total macroscopic cross sections, mean free path and transmission number were calculated for the fast neutron radiation shielding by using (Geant 4) code. In addition to neutron shielding, the gamma absorption parameters such as mass attenuation coefficients (MACs) and half value layer (HVL) were calculated using Win-XCOM software. Sulfuric acid abrasion and compressive strength tests were carried out and all samples showed good resistance to acid wear and pressure force. The neutron equivalent dose was measured using an average 4.5 MeV energy fast neutron source. Results were compared to 316LN type stainless steel, which commonly used in shielding radiation. New stainless steel samples were found to absorb neutron better than 316LN stainless steel at both low and high temperatures.

에칭 폐액으로부터 용매추출과 가수분해를 이용한 니켈분말제조에 관한 연구 (Recovery of Nickel from Waste Iron-Nickel Alloy Etchant and Fabrication of Nickel Powder)

  • 이석환;채병만;이상우;이승환
    • 청정기술
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    • 제25권1호
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    • pp.14-18
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    • 2019
  • 여러 금속 부품을 가공하기 위하여 사용된 염화제이철 에칭 폐액은 유가금속인 니켈 등을 함유하고 있다. 본 연구에서는 식각공정을 완료한 에칭폐액을 재생하고 부산물로 나온 니켈 함유 폐액으로부터 정제하여 니켈 금속분말로 제조하는 공정을 개발하였다. 부산물인 니켈함유용액을 철 등의 불순물을 침전 제거하기 위하여 수산화나트륨 수용액을 실험을 통하여 가수분해 중화제로서 선정하였고, 이를 통하여 철 등의 불순물을 pH = 4 조건하에 침전 제거하였다. 그 후, 불순물로 잔류하는 망간 및 아연과 같은 금속이온들을 D2EHPA (Di-(2-ethylhexyl) phosphoric acid)를 사용하여 용매추출 하였다. 정제된 염화니켈은 99% 이상의 순도를 가지고 있으며, 그 후 환원제로 하이드라진을 이용하여 99% 이상의 순도와 약 150 nm의 크기를 가지는 니켈 금속분말로 제조하였다. 염화니켈 및 니켈 금속분말의 성분은 EDTA 적정법과 유도결합 플라즈마 방출분광법(inductively coupled plasma optical emission spectrometer, ICP-OES)을 이용하여 확인하였으며, 전계방사 주사전자현미경(field emission scanning electron microscope, FE-SEM), X-선 회절분석기(X-ray diffraction, XRD) 및 투과전자현미경(transmission electron microscopy, TEM)을 통하여 금속분말의 형태, 입자 크기 및 결정성과 같은 물리적 특성을 확인하였다.

발전 설비용 CrMo강의 탄화물 구조와 조성 변화에 미치는 열화 및 크리프 손상의 영향 (The Effects of Thermal Degradation and Creep Damage on the Microstructure and Composition of the Carbides in the CrMo Steels for Power Plant)

  • 주연준;홍경태;이현웅;신동혁;김제원
    • 한국재료학회지
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    • 제9권10호
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    • pp.1018-1024
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    • 1999
  • Sn-3.5Ag 무연합금을 Cu 및 Alloy42 리드프레임에 납땜접합 (solder joint)하고 미세조직, 젖음성, 전단강도, 시효효과를 측정하여 비교하였다. Cu의 경우, 땜납의 Sn기지상안에 Ag(sub)3Sn과 Cu(sub)6Sn(sub)5상이, 그리고 땜납/리드프레임의 경계면에서는 1∼2㎛ 두께의 Cu(sub)6Sn(sub)5상이 형성되었다. Alloy42의 경우, 기지상내에 있는 낮은 밀도의 Ag(sub)3Sn상만이, 그리고 계면에는 0.5∼1.5㎛ 두께의 FeSn(sub)2이 형성되었다. 한편, Cu에 비해 Alloy42 리드프레임에서 퍼짐면적은 크고 접촉각은 작아 더 우수한 젖음성을 나타내었으나, 전단강도는 35%, 연신율은 75%로 낮았다. 180℃에서 1주일간 시효처리 후, Cu 리드프레임에는 계면에 η-Cu(sub)6Sn(sub)5 층외에 ξ-Cu(sub)3Sn층이 성장하였고, Alloy42 리드프레임에는 기지상내에 Ag(sub)3Sn이 구형으로 조대하게 성장하였고, 계면에는 FeSn(sub)2층만이 약 1.5㎛로 성장하였다.

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

  • 정근호;조영현;이완로;최근식;이창우
    • 분석과학
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    • 제17권5호
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    • pp.416-422
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    • 2004
  • 시간분해 레이저 유도 파열 분광분석 (TRELIBS) 시스템을 구성하여 원자력발전소 계통재질의 성분을 정성 분석하는 데 응용하였다. 본 연구에서는 탄소강 (A106 Gr. B, A336 P11, A335 P22), 스텐인레스강 (type 304, type 316) 및 인코넬 계열 합금(인코넬 600, 인코넬 690, 인코넬 800) 시료를 사용하였다. 탄소강의 종류는 485~575 nm 파장영역에서 나타난 Cr/Fe과 Mo/Fe의 TRELIBS 피크 비에 의해서 서로 구분 가능하였다. type 304와 type 316 스텐인레스강은 485~575 nm 파장영역에서 나타나는 Mo의 TRELIBS 피크 존재 여부에 의해서 쉽게 구분 가능하였다: type 304는 어떤 Mo의 피크도 나타내지 않지만, type 316은 Mo의 피크를 보여준다. 인코넬 계열 합금강 종류는 420~510 nm 파장영역에서 나타난 Cr/Fe과 Ni/Fe의 TRELIBS 피크비에 의해서 서로 구분 가능하였다. TRELIBS는 시료의 전처리 없이 빠르고 쉽게 합금을 분석할 수 있는 효과적인 분석 기술임이 입증되었다.