• 대한금속재료학회지
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• 제47권2호
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• pp.99-106
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• 2009

The high temperature corrosion properties of heat resistant steels were investigated in oxidation atmosphere including sulfur dioxide. The heat resistant steels of T22, T92, T122, T347HFG and T304H were evaluated at 620, $670^{\circ}C$ for 400 hours. The corrosion rates showed a decreasing tendency while chrome contents of those steels increased from 2 mass.% to 19 mass.%. The in crease in temperature increasement has an more effect on the corrosion rates of low chrome steels than high chrome steels. The weight gains of T22, T92, T304H at $670^{\circ}C$ were 3.7, 1.65, 1.23 times compared with those at $620^{\circ}C$. The external scale formed on T22 was composed of hematite, magnetite and Fe-Cr spinel and internal layer including iron oxide mixed with sulfide. The scales formed on T92, T122, T304H consisted of an outer layer of hematite and inner layer of chrome oxide and hematite. The proportion of chrome oxide at inner layer was increased when the chrome contents in heat resistant steels were increased.

• 한국분말재료학회지
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• 제29권3호
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• pp.240-246
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• 2022

Novel Ni- and Fe-based alloys are developed to impart improved mechanical properties and corrosion resistance. The designed alloys are manufactured as a powder and deposited on a steel substrate using a high-velocity oxygen-fuel process. The coating layer demonstrates good corrosion resistance, and the thus-formed passive film is beneficial because of the Cr contained in the alloy system. Furthermore, during low-temperature heat treatment, factors that deteriorate the properties and which may arise during high-temperature heat treatment, are avoided. For the heattreated coating layers, the hardness increases by up to 32% and the corrosion resistance improves. The influence of the heat treatment is investigated through various methods and is considered to enhance the mechanical properties and corrosion resistance of the coating layer.

• 공업화학
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• 제9권2호
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• pp.268-272
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• 1998

액체금속로 냉각재인 액체 소듐에서 시편의 누출특성을 소듐-물 반응 실험에 의해 조사하였다. 소듐-물 반응 현상의 확인은 물 누출 실험 전후에 Fe, Cr 및 Ni 등과 같은 시편의 조성 변화로 확인하였다. $100kg/cm^2$의 누출 압력으로 4시간 동안 시편의 누출 경로를 통해 물을 누출시킨 결과, 누출경로에서 소듐-물 반응생성물들이 침적되어 있는 것을 확인하였으나, 부식에 의해 누출경로가 완전 파열되어 다량의 수증기가 액체 소듐속으로 빠져나가는 re-openning 현상은 관찰되지 않았다. 시편의 누출경로가 막히는 self-plugging 현상은 소듐-물 반응에 의한 반응생성물과 시편의 부식에 의한 부식 생성물이 주 원인으로 추정되고, re-openning 현상은 시편의 누출경로에서 열적인 transient로 추정되었다.

• 플랜트 저널
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• 제4권2호
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• pp.60-65
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• 2008

As the operating conditions in a supercritical oxidation reactor are set in high temperature with high pressure causing a reactor suffering from the harsh circumstances. It means the reactor adopts itself with Fe-Cr alloy in acidic atmosphere with low pH value and Ni alloy in basic atmosphere with high pH value due to its superior corrosion resistance. The study, whose target waster water is pertinent to the latter part, has selected Ni alloy such as ostenite type stainless steel 304 and 316, superstainless steel AL6XN, Inconel 625, MAT 21, and titanium Gr. 5 in order to measure corrosion resistance against those samples under the same conditions of temperature and pressure applied for a supercritical oxidation reactor. The result shows the identifiable difference in corrosion resistance by observing the surface states through a scanning probe microscope as well as measuring the weight loss through making the samples above deposited in wastewater for two-week and four-week stay. The purpose of this corrosion experiment is to identify the most corrosion-resistant material among sample species pre-selected according to pH concentration of wastewater in pursue of applying for a reactor exposed to the extreme corrosion environment. It is because such a reactor made of a verified material enables to safeguard a stable operation under the supercritical wastewater processing facility.

• Corrosion Science and Technology
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• 제20권4호
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• pp.210-229
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• 2021

To safely operate domestic nuclear power plants approaching the end of their design life, the material degradation management strategy of the components is important. Among studies conducted to improve the soundness of nuclear reactor components, research methods for understanding the degradation of reactor internals and preparing management strategies were surveyed. Since the IGSCC (Intergranular Stress Corrosion Cracking) initiation and propagation process is associated with metal dissolution at the crack tip, crack initiation sensitivity was decreased in the hydrogenated water with decreased crack sensitivity but occurrence of small surface cracks increased. A stress of 50 to 55% of the yield strength of the irradiated materials was required to cause IASCC (Irradiation Assisted Stress Corrosion Cracking) failure at the end of the reactor operating life. In the threshold-stress analysis, IASCC cracks were not expected to occur until the end of life at a stress of less than 62% of the investigated yield strength, and the IASCC critical dose was determined to be 4 dpa (Displacement Per Atom). The stainless steel surface oxide was composed of an internal Cr-rich spinel oxide and an external Fe and Ni-rich oxide, regardless of the dose and applied strain level.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1300-1309
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• 2023

Simulated debris was synthesized using UO₂, Zr, and stainless steel and a heat treatment method under inert or oxidizing conditions. The primary U solid phase of the debris synthesized at 1473 K under inert conditions was UO₂, whereas a (U, Zr)O₂ solid solution formed at 1873 K. Under oxidizing conditions, a mixture of U₃O₈ and (Fe, Cr)UO₄ phases formed at 1473 K, whereas a (U, Zr)O_2+x solid solution formed at 1873 K. The leaching behavior of the fission products from the simulated debris was evaluated using two methods: the irradiation method, for which fission products were produced via neutron irradiation, and the doping method, for which trace amounts of non-radioactive elements were doped into the debris. The dissolution behavior of U depended on the properties of the debris and aqueous solution for immersion. Cs, Sr, and Ba leached out regardless of the primary solid phases. The leaching of high-valence Eu and Ru ions was suppressed, possibly owing to their solid-solution reaction with or incorporation into the uranium compounds of the simulated debris.

• 대한기계학회논문집A
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• 제38권12호
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• pp.1421-1426
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• 2014

소듐냉각고속로(Sodium-cooled Fast Reactor, SFR)의 안전성 향상을 위해 고온 증기 Rankine 싸이클 대신 초임계 이산화탄소(Supercritical $CO_2$, $S-CO_2$) Brayton 싸이클을 전력변환 시스템에 사용하는 방안이 제시되고 있다. 이 경우, 중간 열교환기로는 확산 접합(Diffusion Bonding)에 의해 제작되는 미소채널형 열교환기인 PCHE(Printed Circuit Heat Exchanger)가 고려되고 있다. 따라서 본 연구에서는 PCHE 형 열교환기 후보재료인 다양한 오스테나이트계 합금의 확산접합 특성을 평가하였다. 후보재료별로 다양한 조건에서 확산접합부를 제작하고 상온에서 $650^{\circ}C$까지의 인장 특성을 평가하였다. 평가 결과 SS 316H와 SS 347H는 $550^{\circ}C$까지 모재와 유사한 특성을 보였지만 Fe-Ni-Cr 합금인 Incoloy 800HT는 모든 온도에서 인장특성이 감소하였다. 연신율 저하의 원인을 이해하기 위해 접합부 부근의 미세조직을 분석하였다.

• 한국주조공학회지
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• 제20권5호
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• pp.323-329
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• 2000

The HSS consists of hard carbide and matrix of martensite, and so its characteristics of wear resistance, fracture resistance, and surface roughness are good. This study was undertaken to investigate the influence of Nb and V and manufacturing conditions on microstructural behaviors and characteristics in the HSS cylindrical specimens(90 $mm^{O.D.}$ ${\times}$ 60 $mm^{I.D.}$ ${\times}$ 50 $mm^H$) manufactured using VCC(Vertical Centrifugal Casting). In the specimen of Fe-2C-6Cr-1.5W-3Mo-4V alloy, the amount of MC carbide was increased and $M_7C_3$ carbide was decreased with the increase of V and Nb contents. The primary VC carbide was formed and followed by the rod-type eutectic MC carbide was formed in the cell boundary in 9%V added specimen. MC carbide was increased, and $M_7C_3$ carbide was decreased with the addition of Nb content. In the specimen containing more than 3%Nb, primary NbC carbide was formed within the cell of matrix. With increase in rpm, cell and carbides became fine, and amount of carbide $M_7C_3$ was decreased due to increase in cooling rate.

• 한국분말재료학회지
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• 제22권3호
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• pp.197-202
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• 2015

In this study, porous stainless steel (STS316L) sintered body was fabricated by powder metallurgy method and its properties such as porosity, compressive yield strength, hardness, and permeability were evaluated. 67.5Fe-17Cr- 13Ni-2.5Mo (wt%) powder was produced by a water atomization. The atomized powder was classified into size with under $45{\mu}m$ and over $180{\mu}m$, and then they were compacted with various pressures and sintered at $1210^{\circ}C$ for 1 h in a vacuum atmosphere. The porosities of sintered bodies could be obtained in range of 20~53% by controlling the compaction pressure. Compressive yield strength and hardness were achieved up to 268 MPa and 94 Shore D, respectively. Air permeability was obtained up to $79l/min{\cdot}cm^2$. As a result, mechanical properties and air permeability of the optimized porous body having a porosity of 25~40% were very superior to that of Al alloy.

• 자원리싸이클링
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• 제2권4호
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• pp.1-9
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• 1993

컬럼시기 연속추출장치에 의해 산세폐액으로부터 질산 및 불산을 정제산으로 회수하기 위한 연속실험을 행하였다. 먼저 컬럼식 연속추출장치에 의한 조업시 조업특성을 살펴보면 Pulse Velocity(AxF)가 증가함에 따라 추출율 및 탈거율이 증가하고 잇으나 AxF가 임계치 이상으로 증가하게 되면 수상과 유기상의 강력한 혼합에 의해 분리층이 형성되지 못하고 컬럼전체가 혼합형태가 되어, 효율이 낮아지고 HETS가 길어지게 된다. 또 총유량에 있어 너무 느리게 디면 Backmixing 효과가 나타나게 되고, 반대로 총유량이 매우 빠르게 되면 수상과 유기상의 접촉시간이 불충분하여 효율이 떨어지게 된다. 산세폐액을 컬럼식 연속추출장치로 처리할 경우 추출시에는 70% TBP를 사용하여 상비 A/O=1/2에서 추출하고, 증류수로 상비 1에서 탈거하면 질산 및 불산의 최종회수율은 각각 90.7% 및 75%정도이고 정제산 중 질산농도는 102g/$\ulcorner$ 그리고 불산은 8.8g/$\ulcorner$정도가 된다.