• 제목/요약/키워드: J-weld

검색결과 319건 처리시간 0.025초

Tensile and impact toughness properties of various regions of dissimilar joints of nuclear grade steels

  • Karthick, K.;Malarvizhi, S.;Balasubramanian, V.;Krishnan, S.A.;Sasikala, G.;Albert, Shaju K.
    • Nuclear Engineering and Technology
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    • 제50권1호
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    • pp.116-125
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    • 2018
  • Modified 9Cr-1Mo ferritic steel is a preferred material for steam generators in nuclear power plants for their creep strength and good corrosion resistance. Austenitic stainless steels, such as type 316LN, are used in the high temperature segments such as reactor pressure vessels and primary piping systems. So, the dissimilar joints between these materials are inevitable. In this investigation, dissimilar joints were fabricated by the Shielded Metal Arc Welding (SMAW) process with Inconel 82/182 filler metals. The notch tensile properties and Charpy V-notch impact toughness properties of various regions of dissimilar metal weld joints (DMWJs) were evaluated as per the standards. The microhardness distribution across the DMWJs was recorded. Microstructural features of different regions were characterized by optical and scanning electron microscopy. Inhomogeneous notch tensile properties were observed across the DMWJs. Impact toughness values of various regions of the DMWJs were slightly higher than the prescribed value. Formation of a carbon-enriched hard zone at the interface between the ferritic steel and the buttering material enhanced the notch tensile properties of the heat-affected-zone (HAZ) of P91. The complex microstructure developed at the interfaces of the DMWJs was the reason for inhomogeneous mechanical properties.

Application of the French Codes to the Pressurized Thermal Shocks Assessment

  • Chen, Mingya;Qian, Guian;Shi, Jinhua;Wang, Rongshan;Yu, Weiwei;Lu, Feng;Zhang, Guodong;Xue, Fei;Chen, Zhilin
    • Nuclear Engineering and Technology
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    • 제48권6호
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    • pp.1423-1432
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    • 2016
  • The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the "screening criterion" for maximum allowable embrittlement of RPV material is developed based on the probabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, which are developed based on the deterministic fracture mechanics, there is no "screening criterion". In this paper, the methodology in the RCC-M and RSE-M codes, which are used for PTS analysis, are firstly discussed. The bases of the French codes are compared with ASME and FAVOR codes. A case study is also presented. The results show that the method in the RCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF) may be nonconservative. The SIF almost doubles if the weld residual stress is considered. The approaches included in the codes differ in many aspects, which may result in significant differences in the assessment results. Therefore, homogenization of the codes in the long time operation of nuclear power plants is needed.

Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds

  • Kim, Dong-Jin;Kim, Sung-Woo;Lee, Jong Yeon;Kim, Kyung Mo;Oh, Se Beom;Lee, Gyeong Geun;Kim, Jongbeom;Hwang, Seong-Sik;Choi, Min Jae;Lim, Yun Soo;Cho, Sung Hwan;Kim, Hong Pyo
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.3003-3011
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    • 2021
  • A FAC (flow-accelerated corrosion) test was performed for a straight pipe composed of the SA335 Gr P22 and SA106 Gr B (SA106-SA335-SA106) types of steel with welds as a function of the flow rate in the range of 7-12 m/s at 150 ℃ and with DO < 5 ppb at pH levels ranging from 7 to 9.5 up to a cumulative test time of 7200 h using the FAC demonstration test facility. Afterward, the experimental pipe was examined destructively to investigate opposite effects as well as entrance effects. In addition, the FAC rate obtained using a pipe specimen with a 50 mm inner diameter was compared with the rate obtained from a rotating cylindrical electrode. The effects of the complicated fluid flows at the elbow and orifice of the pipeline were also evaluated using another test section designed to examine the independent effects of the orifice and the elbow depending on the distance and the combined effects on orifice and elbow. The tests were performed under the following conditions: 130-150 ℃, DO < 5 ppb, pH 7 and a flow rate of 3 m/s. The FAC rate was determined using the thickness change obtained from commercial room-temperature ultrasonic testing (UT).

Effects of TiN and B on Grain Refinement of HAZ Microstructure and Improvement of Mechanical Properties of High-strength Structural Steel Under High Heat Input Welding (고강도 구조용 철강소재의 대입열 용접 시 열영향부의 조직 미세화 및 기계적 특성 향상에 미치는 TiN 및 B의 효과)

  • Park, Jin-seong;Hwang, Joong-Ki;Cho, Jae Young;Han, Il Wook;Lee, Man Jae;Kim, Sung Jin
    • Korean Journal of Materials Research
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    • 제29권2호
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    • pp.97-105
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    • 2019
  • In the current steel structures of high-rise buildings, high heat input welding techniques are used to improve productivity in the construction industry. Under the high heat input welding, however, the microstructures of the weld metal (WM) and heat-affected zone (HAZ) coarsen, resulting in the deterioration of impact toughness. This study focuses mainly on the effects of fine TiN precipitates dispersed in steel plates and B addition in welding materials on grain refinement of the HAZ microstructure under submerged arc welding (SAW) with a high heat input of 200 kJ/cm. The study reveals that, different from that in conventional steel, the ${\gamma}$ grain coarsening is notably retarded in the coarse grain HAZ (CGHAZ) of a newly developed steel with TiN precipitates below 70 nm in size even under the high heat input welding, and the refinement of HAZ microstructure is confirmed to have improved impact toughness. Furthermore, energy dispersive spectroscopy (EDS) and secondary-ion mass spectrometry (SIMS) analyses demonstrate that B is was identified at the interface of TiN in CGHAZ. It is likely that B atoms in the WM are diffused to CGHAZ and are segregated at the outer part of undissolved TiN, which contributes partly to a further grain refinement, and consequently, improved mechanical properties are achieved.

Mechanisms of Tolerance to Diphenyl Ether Herbicide Oxyfluorfen in Rice Cultivars (Diphenyl Ether계 제초제 Oxyfluorfen에 대한 벼 품종간 저항성기구)

  • Choi, S.H.;Kim, N.Y.;Lee, J.J.
    • Korean Journal of Weed Science
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    • 제16권4호
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    • pp.362-371
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    • 1996
  • In this study, the relationships between sensitivity to oxyfluorfen, absorption of the herbicide, protoporphyrin IX(Proto IX) accumulation and activities of antioxidative enzymes were examined to identify the tolerance mechanism against oxyfluorfen in various rice cultivars having different level of tolerance to this herbicide. Absorption of oxyfluorfen in tolerant rice cultivars was slower than in susceptible cultivars. Proto IX accumulation in various rice cultivars treated with oxyfluorfen was higher in susceptible cultivars than in tolerant ones. In susceptible cultivars especially, Proto IX accumlated rapidly during the herbicide treatment in the dark. Large amounts of Proto IX accumulation were considered to cause membrane lipid peroxidation in the light. However, among the tested rice cultivars, there was little relationship between their tolerance to oxyfluorfen and the activities of antioxidative enzymes. Therefore, it is assumed that differential susceptibility of rice cultivars to oxyfluorfen was due to difference in their capability to absorb the herbicide and to subsequently accumulate Proto IX.

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Evaluation of Fracture Toughness in Steel Weldment for Inner Wall of LNG Storage Tank (LNG 저장탱크 내조용 강 용접부의 파괴인성 평가)

  • Jang J.-i.;Ju J.-B.;Yang Y.-c.;Kim W.-s.;Hong S. H.;Kwon D.
    • Journal of the Korean Institute of Gas
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    • 제2권1호
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    • pp.7-13
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    • 1998
  • In this study, for the safety performance of LNG storage tank, the fracture toughness in X-grooved weld HAZ(heat-affected zone) of $9\%$ Ni steel was evaluated qualitatively and quantitatively, and the relation with the change in microstructure was analyzed. The toughness assessment was peformed through the modified CTOD test proposed for thick weldment with X-groove. Additionally, microstructures of HAZ were evaluated by OM, SEM and XRD. From the results, HAZ toughness of SMA(shielded metal arc)-welded $9\%$ Ni steel decreased as the evaluated region approached the fusion line. The decrease in toughness was apparently caused by the increase in the fraction of coarse-grained zone within HAZ. On the other hand, toughness drop with decreasing test temperature in F.L.(fusion line) ${\~}$F.L.+3mm was larger than that in F.L.+5mm${\~}$F.L.+7mm region due to the fact that in the former regions, retained austenite had poor stability.

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Sensitivity Analysis of Nozzle Geometry Variables for Estimating Residual Stress in RPV CRDM Penetration Nozzle (원자로 상부헤드 관통노즐의 잔류응력 예측을 위한 노즐 형상 변수 민감도 연구)

  • Bae, Hong Yeol;Oh, Chang Young;Kim, Yun Jae;Kim, Kwon Hee;Chae, Soo Won;Kim, Ju Hee
    • Transactions of the Korean Society of Mechanical Engineers A
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    • 제37권3호
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    • pp.387-395
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    • 2013
  • Recently, several circumferential cracks were found in the control rod drive mechanism (CRDM) nozzles of U.S. nuclear power plants. According to the accident analyses, coolant leaks were caused by primary water stress corrosion cracking (PWSCC). The tensile residual stresses caused by welding, corrosion sensitive materials, and boric acid solution cause PWSCC. Therefore, an exact estimation of the residual stress is important for reliable operation. In this study, finite element simulations were conducted to investigate the effects of the tube geometry (thickness and radius) on the residual stresses in a J-groove weld for different CRDM tube locations. Two different tube locations were considered (center-hole and steepest side hill tube), and the tube radius and thickness variables ($r_o/t$=2, 3, 4) included two different reference values ($r_o$=51.6, t=16.9mm).

Development of Pre-Service and In-Service Information Management System (iSIMS) (원전 가동전/중 검사정보관리 시스템 개발)

  • Yoo, H.J.;Choi, S.N.;Kim, H.N.;Kim, Y.H.;Yang, S.H.
    • Journal of the Korean Society for Nondestructive Testing
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    • 제24권4호
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    • pp.390-395
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    • 2004
  • The iSTMS is a web-based integrated information system supporting Pre-Service and In-Service Inspection(PSI/ISI) processes for the nuclear power plants of KHNP(Korea Hydro & Nuclear Power Co. Ltd.). The system provides a full spectrum coverage of the inspection processes from the planning stage to the final report of examination in accordance with applicable codes, standards, and regulatory requirements. The major functions of the system includes the inspection planning, examination, reporting, project control and status reporting, resource management as well as objects search and navigation. The system also provides two dimensional or three dimensional visualization interface to identify the location and geometry of components and weld areas subject to examination in collaboration with database applications. The iSIMS is implemented with commercial software packages such as database management system, 2-D and 3-D visualization tool, etc., which provide open, updated and verified foundations. This paper describes the key functions and the technologies for the implementation of the iSIMS.

Evaluation of Mechanical Test Characteristics according to Welding Position in FCAW Heterojunction (FCAW 이종접합에서 용접자세에 따른 기계적 시험 특성 평가)

  • Cho, Byung-Jun;Lee, Soung-Jun
    • Journal of the Korea Academia-Industrial cooperation Society
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    • 제20권8호
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    • pp.649-656
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    • 2019
  • Flux cored arc welding (FCAW), which is used widely in many fields, such as shipyards, bridge structures, construction machinery, and plant industry, is an alternative to shielded metal arc welding (SMAW). FCAW is used largely in the welding of carbon and alloy steel because it can be welded in all poses and obtain excellent quality in the field under a range of working conditions. In this study, the mechanical properties of welded parts were analyzed after different welding of SS400 and SM490A using FCAW. The following conclusions were drawn. The tensile test results satisfied the KS standard tensile strength in the range of 400~510 N/mm2 in all welding positions. The bending test confirmed that most of the specimens did not show surface breakage or other defects during bending and exhibited sufficient toughness, even after plastic deformation. The hardness test results were lower than the standard value of 350 Hv of KS B 0893. Similar to the hardness test, were greater than the KS reference value. The macro test revealed no internal flaws, non-metallic inclusions, bubbles or impurities on the entire cross section of the weld, and there were no concerns regarding lamination.