• Title/Summary/Keyword: DMW

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Analytical Evaluation of Residual Stresses in Dissimilar Metal Weld for Cast Stainless Steel Pipe and Low-Alloy Steel Component Nozzle (스테인리스주강 배관과 저합금강 기기노즐 이종금속용접부 잔류응력의 해석적 평가)

  • Park, June-Soo;Song, Min-Seop;Kim, Jong-Soo;Kim, In-Yong;Yang, Jun-Seog
    • Proceedings of the KWS Conference
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    • 2009.11a
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    • pp.100-100
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    • 2009
  • This paper is concerned with numerical analyses of residual stresses in welds and material's susceptibility to stress corrosion cracking (SCC) for the primary piping system in nuclear power plants: Both the dissimilar metal weld (DMW) for stainless steel to low alloy steel joints and the similar metal weld (SMW) for forged stainless steel to cast stainless steel joints are considered. Thermal elasto-plastic analyses using the finite element method (FEM) are performed to predict residual stresses generated in fabrication welding and its related processes for both the DMW and SMW, including effects of quenching for cast stainless steel piping, machining of the DMW root, and grinding of the SMW root. As a result, the effect of quenching should be included in the evaluation of residual stresses in the SMW for the cast stainless steel piping. It is deemed that residual stresses in both the DMW and SMW would not affect the SCC susceptibility of the welds providing that the welding processes are completed without any weld repair on the inside wall of the joint. However, the grinding process if performed on the safe-end to piping weld, would produce a high level of residual stresses in the inner surface region and thus a stress improvement process (e.g. buffing) should be considered to reduce susceptibilities to SCC.

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Computational mechanics and optimization-based prediction of grain orientation in anisotropic media using ultrasonic response

  • Kim, Munsung;Moon, Seongin;Kang, To;Kim, Kyongmo;Song, Sung-Jin;Suh, Myungwon;Suhr, Jonghwan
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1846-1857
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    • 2021
  • Ultrasonic nondestructive testing is important for monitoring the structural integrity of dissimilar metal welds (DMWs) in pressure vessels and piping in nuclear power plants. However, there is a low probability of crack detection via inspection of DMWs using ultrasonic waves because the grain structures (grain orientations) of the weld area cause distortion and splitting of ultrasonic beams propagating in anisotropic media. To overcome this issue, the grain orientation should be known, and a precise ultrasonic wave simulation technique in anisotropic media is required to model the distortion and splitting of the waves accurately. In this study, a method for nondestructive prediction of the DMW grain orientations is presented for accurate simulation of ultrasonic wave propagation behavior in the weld area. The ultrasonic wave propagation behavior in anisotropic media is simulated via finite-element analysis when ultrasonic waves propagate in a transversely isotropic material. In addition, a methodology to predict the DMW grain orientation is proposed that employs a simulation technique for ultrasonic wave propagation behavior calculation and an optimization technique. The simulated ultrasonic wave behaviors with the grain orientations predicted via the proposed method demonstrate its usefulness. Moreover, the method can be used to determine the focal law in DMWs.

Effect of Finite Element Analysis Parameters on Weld Residual Stress of Dissimilar Metal Weld in Nuclear Reactor Piping Nozzles (유한요소 해석변수가 원자로 배관 노즐 이종금속용접부의 용접잔류응력에 미치는 영향)

  • Soh, Na-Hyun;Oh, Gyeong-Jin;Huh, Nam-Su;Lee, Sung-Ho;Park, Heung-Bae;Lee, Seung-Gun;Kim, Jong-Sung;Kim, Yun-Jae
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.8 no.1
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    • pp.8-18
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    • 2012
  • In early constructed nuclear power plants, Ni-based Alloys 82/182 had been widely used for dissimilar metal welds (DMW) as a weld filler metal. However, Alloys 82/182 have been proven to be susceptible to primary water stress corrosion cracking (PWSCC) in the nuclear primary water environment. The formation of crack due to PWSCC is also influenced by weld residual stresses. Thus, the accurate estimation of weld residual stresses of DMW is crucial to investigate the possibility of PWSCC and instability behaviors of crack due to PWSCC. In this context, the present paper investigates weld residual stresses of nuclear reactor piping nozzles based on 2-D axi-symmetric finite element analyses based on layer-based approach using maximum molten bead temperature. In particular, the effect of analysis parameters, i.e., a thickness of weld layer, an initial molten bead temperature, convection heat transfer coefficient, and geometric constraints on predicted weld residual stresses was investigated.

면역독성 평가방법 및 독성기작에 대한 연구

  • 양규환
    • Proceedings of the Korean Society of Applied Pharmacology
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    • 1993.04a
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    • pp.167-167
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    • 1993
  • 신물질의 면역독성 평가방법을 체계화하고 독성기작을 규명하고저 기존 면역독성 유발물질을 대상으로 in vivo 및 in vitro 실험을 수행하였다. 먼저 비장세포-간세포 공동배양 시스템을 대사를 요구하는 물질의 면역독성 평가에 in vitro system으로 사용하고저 DMN을 대상으로 공동배양 조건 및 배지에 대한 연구를 수행하였다. 비장세포원으로 BALB/c 마우스를 사용하였고, 간세포원으로 Spraque-Dawley 랫드를 사용하였다. DMN은 홀몬이 첨가된 배지에서 항체 형성반응을 크게 저하시켰으나 배지의 종류에 따른 DMW의 대사에는 큰 영향이 없었다. 또한 procarcinogen인 DMBA에 의한 면역독성은 DMBA의 대사물에 의해 유도되며 DNA가 primary target 임을 규명하였으며, 2-acetylaminofluorene (AAE)에 의한 면역 억제작용의 기작에서 인터루킨의 영향에 대해 연구하였다. Protein methylase inhibitor인 SF와 SIBA웨 면역억제 작용을 연구한 결과 lymphoproliferative response에서 protein methylase 가 직접 또는 간접적으로 관여함이 입증되었다.

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Six Newly Recorded Fungal Taxa from Freshwater Niche in Korea

  • Lim, Hyo Jin;Nguyen, Thuong T.T;Lee, Hyang Burm
    • Mycobiology
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    • v.49 no.2
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    • pp.105-121
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    • 2021
  • Six interesting fungal strains were isolated during a survey of fungal diversity associated with freshwater; these strains were designated as CNUFC YJW2-22, CNUFC MSW11-6-2, CNUFC HRS5-3, CNUFC MSW242-6, CNUFC DMW2-2, and CNUFC CPWS-1. Based on a polyphasic approach including phylogenetic analyses of internal transcribed space (ITS), large subunit (LSU), beta-tubulin (BenA), and calmodulin (CaM) gene sequences, morphological analyses, the six strains were found to be identical to Acremonium guillematii, Cadophora novi-eboraci, Lectera nordwiniana, Mycoarthris corallina, Talaromyces siamensis, and Tetracladium globosum, respectively. To our knowledge, these are the first records of the rare Lectera, Mycoarthris, and Tetracladium genera in Korea, and the first reports of A. guillematii, C. novi-eboraci, L. nordwiniana, M. corallina, T. siamensis, and Te. globosum in a freshwater environment.

A study on the change of microstructural and mechanical properties by the long-term thermal aging of dissimilar metal welds in nuclear power plants (원전 이종금속 용접부의 장기 열적 시효에 따른 미세조직 및 기계적 특성변화에 관한 고찰)

  • Choi, Kyoung Joon;Yoo, Seung Chang;Kim, Ji Hyun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.82-89
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    • 2014
  • In this study, the metallurgical analysis and mechanical property measurement have been performed to investigate the effect of long-term thermal aging on the microstructural evolution in the fusion boundary region between weld metal and low alloy steel in dissimilar metal welds. A representative dissimilar weld mock-up made of Alloy 690-Alloy 152-A533 Gr. B was fabricated and aged at $450^{\circ}C$ for 2,750 hours. The microstructural characterization was conducted mainly near in a weld root region by using optical microscopy, scanning electron microscopy, transmission electron microscopy. And the mechanical properties were measured with Vickers microhardness test and nanoindentation method. A steep gradient was shown in the chemical composition profile across the interface between A533 Gr. B and Alloy 152. Type-II boundaries were found in weld side of DMW and the hardness was the highest at the narrow zone between Type-II boundary and fusion boundary.

Preliminary Round Robin Test(RRT) for Program for the Inspection of Nickel Alloy Components(PINC) - Reactor Vessel Head Penetration (RVHP) -

  • Kim, Kyung-Cho;Kang, Sung-Sik;Shin, Ho-Sang;Song, Myung-Ho;Chung, Hae-Dong;Kim, Yong-Sik
    • Journal of the Korean Society for Nondestructive Testing
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    • v.29 no.3
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    • pp.256-263
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    • 2009
  • After several PWSCCs were found in Bugey(France), Ringhals(Sweden), Tihange(Belgium), Oconee, Arkansas, Crystal Fever, Davis-Basse, VC Summer(U.S.A.), Thuruga(Japan), USNRC and PNNL started the research on PWSCC, that is, the PINC project. USNRC required KINS to participate in the PINC project in May 2005. KINS organized the Korean consortium at March 2006 and Pre-RRT for RVHP were performed for the preparation of PINC RRT. Through these preliminary RRT, Korea NDE teams can learn and develop the detection and sizing technique for RVHP dissimilar metal weld. These techniques are now being prepared in Korea and need to be utilized for the In-service inspection of the RVHP and BMI of Korea Nuclear Power Plants. PINC RRT mock-ups will be helpful to training.

Welding Residual Stress Distributions for Dissimilar Metal Nozzle Butt Welds in Pressurized Water Reactors (가압경수로 노즐 맞대기 이종금속용접부의 용접잔류응력 예측)

  • Kim, Ji-Soo;Kim, Ju-Hee;Bae, Hong-Yeol;Oh, Chang-Young;Kim, Yun-Jae;Lee, Kyung-Soo;Song, Tae-Kwang
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.36 no.2
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    • pp.137-148
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    • 2012
  • In pressurized water nuclear reactors, dissimilar metal welds are susceptible to primary water stress corrosion cracking. To access this problem, accurate estimation of welding residual stresses is important. This paper provides general welding residual stress profiles in dissimilar metal nozzle butt welds using finite element analysis. By introducing a simplified shape for dissimilar metal nozzle butt welds, changes in the welding residual stress distribution can be seen using a geometry variable. Based on the results, a welding residual stress profile for dissimilar metal nozzle butt welds is proposed that modifies the existing welding residual stress profile for austenitic pipe butt welds.

Preliminary PINC(Program for the Inspection of Nickel Alloy Components) RRT(Round Robin Test) - Pressurizer Dissimilar Metal Weld -

  • Kim, Kyung-Cho;Kang, Sung-Sik;Shin, Ho-Sang;Chung, Ku-Kab;Song, Myung-Ho;Chung, Hae-Dong
    • Journal of the Korean Society for Nondestructive Testing
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    • v.29 no.3
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    • pp.248-255
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    • 2009
  • After several damages by PWSCC were found in the world, USNRC and PNNL(Pacific Northwest National Laboratory) started the research on PWSCC under the project name of PINC. The aim of the project was 1) to fabricate representative NDE mock-ups with flaws to simulate PWSCCs, 2) to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing PWSCCs, 3) to document the range of locations and morphologies of PWSCCs and 4) to incorporate results with other results of ongoing PWSCC research programs, as appropriate. Korea nuclear industries have also been participating in the project. Thermally and mechanically cracked-four mockups were prepared and phased array and manual ultrasonic testing(UT) techniques were applied. The results and lessons learned from the preliminary RRT are summarized as follows: 1) Korea RRT teams performed the RRT successfully. 2) Crack detection probability of the participating organizations was an average 87%, 80% and 80% respectively. 3) RMS error of the crack sizing showed comparatively good results. 4) The lessons learned may be helpful to perform the PINC RRT and PSI /ISI in Korea in the future.

Evaluation for Weld Residual Stress and Operating Stress around Weld Region of the CRDM Nozzle in Reactor Vessel Upper Head (원자로 압력용기 상부헤드 CRDM 노즐 용접부의 용접잔류응력 및 운전응력 평가)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Bae, Hong-Yeol
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.36 no.10
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    • pp.1235-1239
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    • 2012
  • Primary water stress corrosion cracking (PWSCC) has been observed around the weld region of control rod drive mechanism (CRDM) nozzles in nuclear power plants overseas. The weld has a J-shaped groove and it connects the CRDM nozzle with the reactor vessel upper head (RVUH). It is a dissimilar metal weld (DMW), because the CRDM is made of alloy 600 and the RVUH is made of carbon steel. In this study, finite element analysis (FEA) was performed to estimate the stress condition around the weld region. Generally, it is known that a high tensile region is more susceptible to PWSCC. FEA was performed as for the condition of welding, hydrostatic test and normal operation successively to observe how the residual stress changes due to plant condition. The FEA results show that a high tensile stress region is formed around the weld starting point on the inner surface and around the weld stop point on the outer surface.