연구동향 분석

상온과 316℃에서 SA508 Gr.1a 저합금강 배관과 TP316 스테인리스강 배관의 변형거동에 미치는 하중속도의 영향

김진원(Jin Weon Kim) 최명락(Myung Rak Choi) 2015년

논문상세정보
인용/피인용
' 상온과 316℃에서 SA508 Gr.1a 저합금강 배관과 TP316 스테인리스강 배관의 변형거동에 미치는 하중속도의 영향' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • 기계공학
  • deformationbehavior(변형거동)
  • loadingrate(하중속도)
  • sa312 tp316 stainless steel(sa312 tp316 스테인리스강)
  • sa508 gr.1a low alloy steel(sa508 gr.1a 저합금강)
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
931 0

0.0%

' 상온과 316℃에서 SA508 Gr.1a 저합금강 배관과 TP316 스테인리스강 배관의 변형거동에 미치는 하중속도의 영향' 의 참고문헌

  • The Second International Piping Integrity Research Group (IPIRG-2) Program – Final Report
    Hopper, A. [1996]
  • The Effects of Strain Aging due to Interstitial Solutes on the Mechanical Properties of Metals
    Baird, J.D Metall. Reviews 16 : 1 ~ 18 [1971]
  • The Dynamic Tensile Behavior of Tough, Ultra-Strength Steels at Strain-Rates from 0.0002s-1 to 200s-1
    Boyce, B.L. Int. J. Impact Eng. 36 : 263 ~ 271 [2009]
  • The Battelle Integrity of Nuclear Piping (BINP)Program Final Report : 2 ~
    Scott, P. [2005]
  • Summary of the Historical Development of Seismic Design of Nuclear Power Plants in Japan and the U.S.
    Stevenson, J.D. Nucl. Eng. & Design 269 : 160 ~ 164 [2014]
  • Strain Rate Effects in Nuclear Steels at Room and Higher Temperatures
    Solomos, G. Nucl. Eng. & Design 229 : 139 ~ 149 [2004]
  • Standard Test Methods for Tension Testing on Metallic Materials
  • Standard Test Methods for Tensile Strain-Hardening Exponents (n-Values) of Metallic Steel Materials
  • Seismic Safety Evaluation Based on DIP
    Kostov, M. Nucl. Eng. & Design 269 : 256 ~ 261 [2014]
  • Seismic Analysis of RCS with Finite Element Model for Advanced PWR
    Tong, L.L. Prog. Nucl. Energy 79 : 142 ~ 149 [2015]
  • Seismic Analysis of Large-Scale Piping Systems for the JNES-NUPEC Ultimate Strength Piping Test Program
  • Mechanical Metallurgy
    Diter, G.E. McGraw-Hill : 283 ~ 301 [1988]
  • Effect of Dynamic Strain Aging on the Strength and Toughness of Nuclear Ferritic Piping at LWR Temperatures
  • An Introduction to Nuclear Materials – Fundamental and Applications
    Murty, K.L. Wiley-VCH : 193 ~ 195 [2009]
  • An Approach to the Quantification of Seismic Margins in Nuclear Power Plants
  • ASME B&PV Code Sec.XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,”
  • ASME B&PV Code Sec.III, “Nuclear components,”