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      KCI등재후보

      냉간가공을 통한 중성자조사된 오스테나이트 스테인리스강의 기계적물성 모사 타당성 분석 = Feasibility Analysis of Simulation on the Mechanical Properties of Neutron Irradiated Austenitic Stainless Steels by Cold-working

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      https://www.riss.kr/link?id=A106491822

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      다국어 초록 (Multilingual Abstract)

      The objective of this study is to investigate the feasibility of simulating the mechanical properties of irradiatied austenitic stainless steels by cold-working. In this study, the tensile properties, cyclic hardening behaviors and fracture toughness ...

      The objective of this study is to investigate the feasibility of simulating the mechanical properties of irradiatied austenitic stainless steels by cold-working. In this study, the tensile properties, cyclic hardening behaviors and fracture toughness of cold-worked TP316L stainless steel were compared with those of austenitic stainless steels irradiated by neutrons. It showed that cold-working can properly simulate the increase in strength and the decrease in ductility and fracture resistance of austenitic stainless steels by neutron irradiation, even though it could not perfectly simulate the microstructures of irradiated austenitic stainless steels. Also, cold-working can appropriately simulate the hardening behaviors of neutron irradiated austenitic stainless steels under monotonic and cyclic loading conditions.

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      참고문헌 (Reference)

      1 최명락, "원전 구조재료의 반복 변형거동에 미치는 경년열화 영향 평가" 대한기계학회 42 (42): 239-246, 2018

      2 J.-S. Kim, "Structural Integrity Analysis of Lower Core Plate in Pressurized Water Reactors Considering Stress Triaxiality" Elsevier BV 130 : 1494-1502, 2015

      3 Edward A. Kenik, "Radiation-induced degradation of stainless steel light water reactor internals" Elsevier BV 73 (73): 67-83, 2012

      4 Chungseok Kim, "Nondestructive Evaluation of Strain-Induced Phase Transformation and Damage Accumulation in Austenitic Stainless Steel Subjected to Cyclic Loading" MDPI AG 8 (8): 1-14, 2018

      5 EPRI, "Materials Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data-State of Knowledge" Electric Power Research Institute 2007

      6 Surajit Kumar Paul, "Key issues in cyclic plastic deformation: Experimentation" Elsevier BV 43 (43): 705-720, 2011

      7 Jin Weon Kim, "J–R fracture toughness of cold-worked TP316L stainless steel under seismic loading conditions" Elsevier BV 171 : 137-144, 2019

      8 J.E. Pawel, "Irradiation performance of stainless steels for ITER application" Elsevier BV 239 : 126-131, 1996

      9 Choi, K.J, "Investigation of Warm Rolling and Dissolved Hydrogen on Crack Growth Rate of 316L Austenitic Stainless Steel in Promary Water Condition" 19 (19): 21-22, 2015

      10 Murty, K.L., "Introduction to Nuclear Materials – Fundamentals and Applications" Wiley 2012

      1 최명락, "원전 구조재료의 반복 변형거동에 미치는 경년열화 영향 평가" 대한기계학회 42 (42): 239-246, 2018

      2 J.-S. Kim, "Structural Integrity Analysis of Lower Core Plate in Pressurized Water Reactors Considering Stress Triaxiality" Elsevier BV 130 : 1494-1502, 2015

      3 Edward A. Kenik, "Radiation-induced degradation of stainless steel light water reactor internals" Elsevier BV 73 (73): 67-83, 2012

      4 Chungseok Kim, "Nondestructive Evaluation of Strain-Induced Phase Transformation and Damage Accumulation in Austenitic Stainless Steel Subjected to Cyclic Loading" MDPI AG 8 (8): 1-14, 2018

      5 EPRI, "Materials Reliability Program: PWR Internals Age-Related Material Properties, Degradation Mechanisms, Models, and Basis Data-State of Knowledge" Electric Power Research Institute 2007

      6 Surajit Kumar Paul, "Key issues in cyclic plastic deformation: Experimentation" Elsevier BV 43 (43): 705-720, 2011

      7 Jin Weon Kim, "J–R fracture toughness of cold-worked TP316L stainless steel under seismic loading conditions" Elsevier BV 171 : 137-144, 2019

      8 J.E. Pawel, "Irradiation performance of stainless steels for ITER application" Elsevier BV 239 : 126-131, 1996

      9 Choi, K.J, "Investigation of Warm Rolling and Dissolved Hydrogen on Crack Growth Rate of 316L Austenitic Stainless Steel in Promary Water Condition" 19 (19): 21-22, 2015

      10 Murty, K.L., "Introduction to Nuclear Materials – Fundamentals and Applications" Wiley 2012

      11 Masayuki Kamaya, "Elastic-plastic failure assessment of cold worked stainless steel pipes" Elsevier BV 131 : 45-51, 2015

      12 Devries, M.I, "Effects of neutron irradiation on low-cycle fatigue and tensile properties of AISI Type 304 stainless steel at 298K" 1 : 159-171, 1979

      13 Facheris, G., "Cyclic plastic material behavior leading to crack initiation in stainless steel under complex fatigue loading conditions" Politecnico di Milano 2014

      14 Shiro Jitsukawa, "Comparison of elastic—plastic fracture toughness of irradiated and cold-worked JPCA using miniaturized DCT specimens" Elsevier BV 233-237 : 152-155, 1996

      15 M. Matijasevic, "Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C" Elsevier BV 377 (377): 101-108, 2008

      16 IAEA, "Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals"

      17 Shah, V.N., "Aging and Life Extension of Major Light Water Reactor Components" Elsevier Science Pub. 1993

      18 "ASTM E8/E8M-09, “Standard test method for tension testing of metallic materials”"

      19 "ASTM E606-92, Standard Practice for Strain-Controlled Fatigue Testing"

      20 "ASTM E1820-15, “Standard test method for measurement of fracture toughness”"

      21 O.K. Chopra, "A review of irradiation effects on LWR core internal materials – Neutron embrittlement" Elsevier BV 412 (412): 195-208, 2011

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