[보고서]압력경계 재료열화 파괴역학적 대응기술 개발

김민철

보고서 정보

주관연구기관

한국원자력연구원
Korea Atomic Energy Research Institute

연구책임자

김민철

참여연구자

공운식 , 최권재 , 김종민 , 김경모 , 권준엽 , 김흥회 , 홍석민 , 이봉상 , 김우곤

보고서유형

1단계보고서

발행국가

대한민국

언어

한국어

발행년월

2020-01

과제시작연도

2019

주관부처

과학기술정보통신부
Ministry of Science and ICT

등록번호

TRKO202000001823

과제고유번호

1711081813

사업명

원자력기술개발사업(R&D)

DB 구축일자

2020-07-29

키워드

원자로용기.조사취화.파괴인성.소형펀치시험.전열관파손.RPV.Irradiation Embrittlement.Fracture Tough ness.Small Punch Test.SG Tube Rupture.

표 Chemistry of RPV steel of Kori unit 2 and Hanbit unit 2 in wt%
표 Summary of tensile test results for Kori unit 2 base metal and weld
표 Summary of tensile test results for Hanbit unit 2 base metal
표 Summary of Charpy impact test results for Kori unit 2 base metal and weld
표 Summary of Charpy impact test results for Hanbit unit 2 base metal
표 Test materials from nozzle section of reactor pressure vessels in Kori unit 2 & Hanbit unit 2
표 Block of archive material used m this study and schematic drawing for sample locations
표 Schematic drawing for test specimens: (a) rod-type tensile, (b) ST-PCVN, (c) Charpy impact, (d) 1/2T-CT
표 OM microstructure images of K2 base materials in 1/10T and 1/4T positions according to the sample directions
표 SEM microstructure images of K2 base materials m 1/10T and 1/4T positions according to the sample directions
표 OM microstructure images of K2 base materials in 1/10T, 1/4T, 1/2T, 3/4T, and 9/10T positions
표 SEM microstructure images of K2 base materials in 1/10T, 1/4T, 1/2T, 3/4T, and 9/10T positions
표 Comparison of OM microstructure images of K2, HU3, and BNPP4 base materials
표 Comparison of OM microstructure images of K2, HU3, and BNPP4 base materials
표 Comparison of microstructure images of K2 base and weld materials
표 Tensile properties of Kori unit 2 base at RT and 288°C as a function of specimen depth
표 Tensile properties of Hanbit unit 2 base at RT and 288°C as a function of specimen depth
표 Charpy transition curves of Kori unit 2 base
표 Changes in index temperature, T41J, T68J as a function of specimen depth of Kori unit 2
표 Charpy transition curves of Hanbit unit 2 base
표 Changes in index temperature, T41J, T68j as a function of specimen depth of Hanbit unit 2
표 Fracture toughness of Kori unit 2 RPV in transition region
표 Fracture toughness of Hanbit unit 2 RPV in transition region
표 J-R Curves of Kori Unit 2 (Base Metal)
표 J-R Curves of Kori Unit 2 (Weld Metal)
표 J-R Curves of Hanbit Unit 2 (Base Metal)
표 Specimen type, quantity, and location of 17M-01K instrumented irradiation capsule for CT hole irradiation at HANARO
표 Neutron irradiation results for 17M-01K capsule
표 Irradiation temperature of 17M-01K capsule
표 Summary of tensile test results for Kori unit 2 weld and Hanbit unit 2 base
표 Specimen arrangement layout and final product of capsule
표 Stress-strain curves of Kori unit 2 weld and Hanbit unit 2 base before and after irradiation
표 Comparison of Master Curve toughnesses between pre-irradiated and post-irradiated Hanbit unit 2 RPV steel
표 Transition temperature shifts from survelliance tests and 17M-01K
표 Comparison of J-R Test Results for Kori Unit 2
표 Chemistry Factor for Base Metal(R.G. 1.99 Rev.2)
표 Number of Data used for the Analysis of Irradiation Embrittlement Trend Curves in Domestic Power Plants
표 TTS vs. Fluence (Domestic Surveillance Data)
표 TTS vs. Fluence (USA Surveillance Data)
표 Comparison of Changes in Fluence-ΔT30 by Material Form, Country and Cu Contents
표 Comparison of Changes in Fluence-ΔT30 by Material Form, Country and low Cu Contents
표 Measured ΔT30 vs. Predicted ΔT30 Based on R.G. 1.99 Rev. 2
표 Measured ΔT30 vs. Predicted ΔT30 Based on EWO
표 Measured ΔT30 vs. Predicted ΔT30 Based on R.G. 1.99 Rev. 3
표 Measured ΔT30 vs. Predicted ΔT30 Based on WR-C(5)
표 Measured ΔT30 vs. Predicted ΔT30 Based on ASTM E900-15e1
표 Fluence Effect based on R.G. 1.99 Rev. 2
표 Fluence Effect based on EWO
표 Fluence Effect based on R.G. 1.99 Rev. 3
표 Fluence Effect based on WR-C(5)
표 Fluence Effect based on ASTM E900-15e1
표 Laboratories and countries participated in ILS1408
표 Materials used in ILS1408 Interlaboratory study
표 Comparison of load diagrams and SP parameters of material 1a after SP testing with different test rig (radius or chamfer shape in the corner of the receiving die)
표 Cross-sectional scheme of the Test rig (1-Test specimen, 2-punch, 3-receiving die, 4-clamping die, and 5- deflection measurement rod
표 Load-deflection curve recorded during a SP test of a ductile material
표 Number of documents in SCOPUS relating to “small punch”
표 SP test rig and SP test instrument
표 Developed SP DATA analysis program
표 SP Load-deflection curves of A533 B materials (1a, and 1b) used in ILS1408 interlaboratory study testing
표 Load-deflection curves of ILS1408 interlaboratory study test materials
표 Comparison of SP test method between WK61832 and pre-performed KAERI SP test
표 Empirical constant βYS and R2
표 Empirical constant βUTS, Y, and value of R2
표 Empirical constant αUTS, Y, and value of R2
표 Empirical constant α and value of R2 obtained from TSP = α • TCVN fitting curve
표 Empirical constant α , β and value of R2 obtained from TSP = α • TCVN + β fitting curve
표 SP load-displacement curves of RPV materials at different temperature
표 FEM SP test result with different receiving die shape; round and chamfer
표 SP test result with different receiving die shape; round and chamfer
표 FEM simulation result of K-SP method and WK61832 SP method
표 FEM simulation Load-dis./def curves of K-SP method and WK61832 draft standard SP method
표 SP test Load-displacement curves of K-SP method and WK-SP method
표 All methods for determining SP yield point in literature survey
표 Correlation between Fe / h02 parameters and Yield strength of each RPV materials
표 Correlation between Fe / h02 parameters and Yield strength using all RPV material data
표 Correlation between Fm/(h0*um) parameters and Tensile strength; (a) UTS = βUTS. Fm/(h0.um) fitting, (b) UTS = βUTS. Fm/(h0.um)+Y
표 Correlation between Fm/(h0*um) parameters and Tensile strength; (a) UTS = βUTS. Fm/(h0.um) fitting, (b) UTS = βUTS. Fm/(h0.um)+Y
표 Correlation between Fm/(h0 • um) parameters and Tensile strength
표 SP FEM simulation force-displacement curves when input the different tensile curves shape with same tensile strength
표 Correlation between Fi/h02 parameters and tensile strength
표 Correlation between Fi/(h02) parameters and Tensile strength
표 Determination of Tsp using SP energy and normalized SP energy
표 SP ductile-brittle transition curves obtained from the SF Fracture energy vs. temperature data
표 SP ductile-brittle tran sition curves obtained from the normalized SP energy vs. temperature data
표 Correlation between Tsp parameters (ESP_DBTT, ESP_1.2J, En_DBTT) and CVN transition temperature (TCVN_41J, TCVN_DBTT)
표 Fractured SP specimen images and SP Fractograph at different temperatures
$Distinguishing the ductile, ductile to brittle, and brittle fracture mo section in normalized ESP vs. temperature curves$ 표 Distinguishing the ductile, ductile to brittle, and brittle fracture mo section in normalized ESP vs. temperature curves
$Distinguishing the ductile, ductile to brittle, and brittle fracture mode section in normalized post necking elongation (DND) vs. temperature curve$ 표 Distinguishing the ductile, ductile to brittle, and brittle fracture mode section in normalized post necking elongation (DND) vs. temperature curve
표 Correlation between TSP parameters (En-0.5, DND_0.01)and CVN transition temperature (TCVN_41)
표 Data Sheet for RBF Analysis
표 Neural Network-based Approximation
표 Analysis of Local Parameter Effect on Fracture Toughness
표 Derived Parameter Sets for SP Damage Model
표 Typical FE Model for SP Test and L-d Curve
표 Comparison of L-d Curve of Experiment and FE Analysis Results (By DOE and XFEM)
표 Test Matrix for Const. T, Ramp P Tests
표 Test Matrix for Const. P Rupture Tests
표 Test Matrix for Const. P, Ramp T Tests
표 Test Matrix for Preliminary Failure Tests
표 Tensile test results of Alloy 690 SG tube
표 Coefficient of expansion of Alloy 690 measured by dilatometer
표 Specific heat of Alloy 690 measured by DSC and LFA
표 Conductivity of Alloy 690 measured by LFA
표 Diffusivity and Sensitivity of Alloy 690 measured by LFA and DSC
표 Specimen shapes and test equipment for the tensile test of steam generator tube
표 Stress-strain curves of alloy 690 tube at different test temperature
표 Temperature dependency of Yield & Tensile strength
표 Ring-Type Circumferential Specimens for Tensile Test
표 Ring-Type Circumferential Specimens for Tensile Test
표 Typical Specimen After Failure
표 FE Model for Simulation of Experiments
표 Flow Chart for FE Analysis and Optimization
표 Load-Displacement Response of the Alloy 690 Ring-Type Specimen with 3-Piece Loading Mandrels
표 True Stress-True Plastic Strain Curves of Alloy 690 SG Tube in Axial Direction From the Test and Circumferential Direction From the FE Simulation & Optimization Technique
표 Image Quality Map of Alloy 690 SG Tube
표 Inverse Pole Figure (IPF) of Alloy 690 SG Tube
표 Schematic drawing for SG tube rupture tester
표 SG tube rupture tester
표 Specimen for SG tube rupture test
표 Image of tested specimen during preliminary test
표 SG Tube Material in Domestic NPP
표 Relative Error Between Predicted and Observed Failure Pressures In PNNL Tests for Various mp Models
표 Chemical Composition of Alloy 690 SG Tube(CMTR)
표 Tensile Property of Alloy 690 Tube in Various Temperature
표 Experimental Conditions and Results of Creep Tests
표 Parameter Comparison(KAERI+INCO data vs. KAERI data)
표 Risk of Radioactive Release and Temperature Profile of SG tube in Severe Accident Conditions
표 Average Number of Flaws as a Function of EFPY for Four SGs(Prediction)
표 Magnification Factor mp as computed by BCL, ANL, INEL, and EdF Equations as a Function of Crack Length for Crack Depth-to-thickness Ratios : (a) a/h=0.5, (b) a/h=0.9
표 (a) True Stress-strain Curve Used in Finite-element Analysis a nd (b) Variation of Calculated Hoop Stress Enhancement Factor in the Ligament with Pressure for a 22mm dia. Tube with Two Axial Part-through Crack Geometries at 300 and 750°C
표 Geometry of Specimen for Tensile and Creep Test
표 Photo of Pin-type Creep Specimen
표 Test Set-up for Creep Tests
표 Creep Curves of Alloy 690 Tested at 700-850°C
표 Plot of Log Stress Versus Log Rupture Time Obtained for the Alloy 690 at Various Temperatures(Test) with Data of Manufacturer
표 M-G Relationship of Alloy 690 Tube(Test Results)
표 Determination of LMP
표 LMP According to the Change of Constant C value
표 Determination of Optimal C value : (a) Root-mean-square, (b) Master Curve of LMP
표 Determination of Q/2.3R for OSD Method
표 Master Curve of OSD Method
표 Determination of logta and Ta for MH Method
표 Master Curve of MH Method
표 Determination of Q* for Wilshire Approach
표 Curve Fitting of Wilshire Approach
표 Creep Life Prediction of LM Method as a function of 3rd Polynomial Master Curve
표 Creep Life Prediction of OSD Method as a function of 3rd Polynomial Master Curve
표 Creep Life Prediction of MHP Method as a function of 3rd Polynomial Master Curve
표 Creep Life Prediction of LM Method as a function of ＂sinh＂ Master Curve
표 Creep Life Prediction of OSD Method as a function of “sinh” Master Curve
표 Creep Life Prediction of MHP Method as a function of “sinh” Master Curve
표 Creep Life Prediction of Wilshire Approach
표 Comparison of Creep Life (KAERI vs. Manufacturer(plate in the as-hot-rolled condition))
표 Comparison of Predicted Failure Temperatures
표 Effects of (a) Loading Rate on Failure Pressure in Isothermal Burst Test and (b) Temperature Ramp on Failure Temperature in Burst Test at a Constant Pressure of 16 MPa of Unflawed 22 mm dia. Alloy 600 Tube. Also shown are predicted failure pressures and temperatures by flow stress model (dashed lines) using INEL flow stress curve and by ANL creep rupture model (solid lines)
표 Flow Stress Curves(using k=0.5) for various product forms of Alloy 600
표 Comparison of Flow Stress Curve with Pressure Ramp Test Results on Flawed and Unflawed Tubes
표 Bilinear Fit to Existing Creep Data for Alloy 600
표 Comparison of the Current Correlation Used in SCDAP with Existing Data
표 Comparison of the Experimental and Predicted Times to Rupture of Unflawed Alloy 600 Tubing under Constant Internal Pressure(Tests were conducted isothermally and under constant temperature ramps of 0.2°C /min, 2°C/min, and 20℃/min)
표 Comparison of Predicted (by Flow Stress Model) Versus Observed (a) Failure Temperatures and (b) Times to Failure for High Temperature Rupture Tests Conducted with the IN E L and EPRI Temperature Ramps

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압력경계 재료열화 파괴역학적 대응기술 개발
Development of advanced fracture mechanics technology for integrity assurance of reactor pressure boundary materials 원문보기

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압력경계 재료열화 파괴역학적 대응기술 개발 Development of advanced fracture mechanics technology for integrity assurance of reactor pressure boundary materials 원문보기

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압력경계 재료열화 파괴역학적 대응기술 개발
Development of advanced fracture mechanics technology for integrity assurance of reactor pressure boundary materials 원문보기

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