http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
주조 스테인리스강 CF8M의 43$0^{\circ}C$ 열화거동에 관한 연구 (II) -저사이클 피로특성 평가-
권재도,우승완,박중철,이용선,박윤원,Gwon, Jae-Do,U, Seung-Wan,Park, Jung-Cheol,Lee, Yong-Seon,Park, Yun-Won 대한기계학회 2000 大韓機械學會論文集A Vol.24 No.9
A thermal aging is observed in a primary reactor cooling system(RCS) made of a casting stainless steel when the RCS is exposed for long period at the reactor operating temperature, 290~3300C An investigation of effects of thermal aging on a low cycle fatigue characteristics included a stress variations caused by a reactor operation and trip, is required. The purpose of the present investigation is to find an effect of a thermal aging of the CF8M on a low cycle fatigue life. The specimen of CF8M are prepared by an artificially accelerated aging technique holding 300 and 1800hr at 4300C respectively. The low cycle fatigue tests for the virgin and two aged specimens are performed at the room temperature for various strain amplitudes($\varepsilon$ta), 0.3, 0.5, 0.8, 1.0, 1.2 and 1.5% strain. Through the experiment, it is found that the fatigue life is rapidly reduced with an creasing of the aging time. The experimental fatigue life estimation formulas between the virgin and two aged specimen are obtained and are proposed to a analysis purpose.
순수 비틀림 하중하에서 열화를 고려한 2상 스데인리스강의 저주기 피로특성
권재도,박중철,Gwon, Jae-Do,Park, Jung-Cheol 대한기계학회 2002 大韓機械學會論文集A Vol.26 No.9
Monotonic torsional and pure torsional low cycle fatigue(LCF) test with artificial degradation were performed on duplex stainless steel(CF8M). CF8M is used in pipes and valves in nuclear reactor coolant system. It was aged at 430$^{\circ}C$ for 3600hrs. Through the monotonic and LCF test, it is found that mechanical properties(i.e., yield strength, strain hardening exponent, strength coefficient etc.) increase and fatigue life(N$\sub$f/) decreases with degradation of material. The relationship between shear strain amplitude(${\gamma}$$\sub$a/)and N$\sub$f/ was proposed.
주조 스테인리스강 CF8M의 43$0^{\circ}C$ 열화거동에 관한 연구 (III) - 탄소성 파괴인성 평가 -
권재도,인재현,박중철,최성종,박윤원,Gwon, Jae-Do,In, Jae-Hyeon,Park, Jung-Cheol,Choe, Seong-Jong,Park, Yun-Won 대한기계학회 2000 大韓機械學會論文集A Vol.24 No.10
A cast stainless steel may experience an embrittlement when it is exposed to approximately 30$0^{\circ}C$ for long period. In the present investigation, The three classes of the thermally aged CF8M specimie n are prepared using an artificially accelerated aging method. Namely, after the specimen are held for 300, 1800 and 3600hrs. at 43$0^{\circ}C$ respectively, the specimens are quenched in water to room temperature. Load versus load line displacement curves and J-R curves are obtained using the unloading compliance method. $J_{IC}$ values are obtained following ASTM E 813-87 and ASTM E 813-81 methods. In addition to these methods, JIC values are obtained using SZW(stretch zone width) method described in JSME S 001-1981. The results of the unloading compliance method are $J_Q$=485.7 kJ/m$^2$ for virgin material, $J_{IC}$ of the degraded materials associated with 300, 1800 and 3600hrs are obtained 369.25 kJ/m$^2$, 311.02 kJ/m$^2$, 276.7 kJ/m$^2$, respectively. The results of SZW method are similar to those of the unloading compliance method. Through the elastic-plastic fracture toughness test, it is found that the value of $J_{IC}$ is decreased with increasing of the aging time. The results obtained through the investigation can provide reference data for a leak before break(LBB) of reactor coolant system of nuclear power plants.
주조 스테인리스강 CF8M의 43$0^{\circ}C$ 열화거동에 관한 연구(I);열화기구.정적 및 피로강도평가
권재도,박중철,이용선,이우호,박윤원,Gwon, Jae-Do,Park, Jung-Cheol,Lee, Yong-Seon,Lee, U-Ho,Park, Yun-Won 대한기계학회 2000 大韓機械學會論文集A Vol.24 No.8
The five classes of the thermally aged CF8M specimen are prepared using an artificially accelerated aging method. Namely, after the specimens are held for 100, 300, 900, 1800, and 3600hrs at 430$^{\circ}C$ respectively, the specimens are water-cooled to room temperature. The impact energy variations are measures for both the aged and virgin specimens through the Charpy impact tests in addition to the microstructure observation, tensile, hardness and fatigue crack growth tests. From the present investigation the following results are obtained : 1) The difference among the thermally degraded specimens can be distinguished through their microstructures, 2) Hardness and tensile strength are increased to 300hrs, degradation specimen, while elongation and reduction area are decreased to 3600hrs degradation specimen, and impact energy is decreased to 1800hrs degradation specimen, 3) The FCG rates for thermally degraded specimens are larger than that of the virgin specimen.
김용기(Yong-Ki Kim),장세기(Seky Chang) 한국철도학회 2005 한국철도학회논문집 Vol.8 No.6
Fatigue life of catenary wires in various environments is reduced when stress is concentrated on some points, which are often found in corroded areas by surrounding pollutants. Therefore, the fatigue test were performed in order to investigate the effect of the surface corrosion on the destructive behavior in service environment and accelerated corrosion environment as well as to examine the corrosive property and mechanism of the catenary wires. In the fatigue test of the messenger stranded wire, the corrosion degraded materials showed 35~50% of fatigue life at a same stress amplitude compared to original material. Because the catenary wires have variable load by the interaction of periodic contacts with pantographs the maximum stresses of trolley wire and messenger wire calculated by simulation at the operative velocity, 80km/h, were 11.4kgf/m㎡ and 11.62kgf/m㎡, respectively. In conclusion, the life prediction of the messenger wire during operation was estimated through the corrosion behavior interpretation of variable stress and fatigue test.