Temper-Bead Weld Heat-Affected Zone Properties in A516-70 Steel

1987 ◽  
Vol 109 (2) ◽  
pp. 157-163 ◽  
Author(s):  
Y. J. Kim ◽  
J. W. Prince
Keyword(s):  
Fracture Toughness ◽  
Heat Affected Zone ◽  
Fracture Toughness Test ◽  
Test Results ◽  
Weld Repair ◽  
Metallographic Examination ◽  
Series Of Experiments ◽  
Hardness Values ◽  
Welding Technique ◽  
Weld Heat

A temper-bead welding technique has been developed to provide an alternative weld repair method in which the application of a high temperature post-weld heat treatment (PWHT) can be avoided. In order to assess the integrity of temper-bead weld repairs, a series of experiments were carried out on a simulated temper-bead weld made on A516-70 steel plate. Metallographic examination of the weld repair shows that the temper-bead technique can produce a grain refined heat-affected zone (HAZ) microstructure with acceptable hardness values. The JIC fracture toughness test results show that the HAZ exhibited equivalent or greater fracture toughness than the base metal.

Experimental Investigation on Relative Crack Length For Fracture Toughness of Concrete

2010 ◽  
Vol 146-147 ◽  
pp. 1524-1528 ◽  
Author(s):  
Xue Zhi Wang ◽  
Zong Chao Xu ◽  
Zhong Bi ◽  
Hao Wang
Keyword(s):  
Fracture Toughness ◽  
Experimental Investigation ◽  
Crack Length ◽  
Fracture Toughness Test ◽  
Test Results ◽  
Toughness Test ◽  
Wedge Splitting Test ◽  
Splitting Test ◽  
Wedge Splitting

The wedge splitting test specimens with three series of different relative crack length were used to study the influences of relative crack length on the fracture toughness of common concrete. The suitable formulation for fracture toughness of concrete with different relative crack length was gotten on comparing between fracture toughness test results and computation results of the model developed from Hu formula.

Fracture Toughness of Stainless Steel Cladding for Evaluation of the Degraded Davis-Besse RPV Head

2006 ◽  
Author(s):  
Randy K. Nanstad ◽  
Mikhail A. Sokolov
Keyword(s):  
Fracture Toughness ◽  
Stainless Steel ◽  
Pressure Vessel ◽  
National Laboratory ◽  
Nuclear Regulatory Commission ◽  
Shear Mode ◽  
Fracture Toughness Test ◽  
Test Results ◽  
Acid Attack ◽  
Oak Ridge

Boric acid attack in the reactor pressure vessel (RPV) head of the Davis-Besse (D-B) nuclear plant led to wastage through the 150-mm low alloy steel head such that the stainless steel cladding was exposed. The Heavy-Section Steel Technology (HSST) Program at Oak Ridge National Laboratory was commissioned by the Nuclear Regulatory Commission to conduct a program of testing and analysis to enable an evaluation of the structural significance of cladding defects found in the wastage cavity of the D-B head. The overall test program consisted of material characterization at 316°C (600°F) of cladding materials, pressure vessel burst tests of cladding discs with and without flaws, and extensive analytical studies. Three different cladding materials were tested and evaluated, one from an unused commercial RPV that was used for the clad-burst experiments, an archival cladding previously used for various experimental and irradiation experiments, and the cladding from the D-B head. This paper compares and discusses the fracture toughness test results conducted with the three claddings, and the fractographic analyses conducted on the clad-burst discs. Comparison of J-resistance curves for the three clad materials shows significant material variability and disparity in the results from two test specimen types. Fractographic examinations of clad-burst discs showed transition from ductile tearing to shear mode of fracture. The relationship of the cladding test results with the clad-burst results is discussed.

Crack Arrest Test Results of Unirradiated and Irradiated German RPV Steels

2013 ◽  
Author(s):  
Florian Obermeier ◽  
Julia Barthelmes ◽  
Elisabeth Keim ◽  
Hieronymus Hein ◽  
Hilmar Schnabel ◽  
...  
Keyword(s):  
Fracture Toughness ◽  
Lower Bound ◽  
Pressure Vessel ◽  
Charpy Impact ◽  
Crack Arrest ◽  
Reactor Pressure Vessel ◽  
Test Method ◽  
Fracture Toughness Test ◽  
Test Results ◽  
Reactor Pressure

In the CARISMA[1] and CARINA[2] projects comprehensive tensile, Charpy-impact and fracture toughness tests were performed for unirradiated and irradiated original reactor pressure vessel (RPV) steel specimens from German pressurized water reactors (PWR) up to neutron fluences in the range of 60 operational years and beyond. In addition, crack arrest fracture toughness tests were performed to demonstrate the crack arrest behavior of the materials. To determine the crack arrest properties of ferritic steels, the designated test method according to ASTM E1221 [3] was used. However, in particular for irradiated reactor pressure vessel materials with higher irradiation embrittlement, the prescribed standard test specimen does not always provide adequate test results. During starter notch preparation annealing effects occurred in the heat affected zone (HAZ) of the brittle weld of the starter notch causing crack arrest in the HAZ after unstable crack initiation. Therefore a modified test method to perform crack arrest tests with so called duplex specimens was investigated. In this paper this modified method and the test results of five base and four weld metals with a fluence up to 4,69E+19 cm−2 (E >1 MeV) are discussed. The available test results show that the duplex specimen is an appropriate alternative to the standard compact crack arrest (CCA) specimen. The measured KIa fracture toughness data are enveloped by the “lower bound” of the ASME KIa-curve indexed with RTNDTj or TKIa but not all data are enveloped by indexing the “lower bound” curve with RTT0 like described in the ASME Code Case N-629 [4]. Furthermore correlations of the crack arrest test results with Charpy-impact and fracture toughness test results will be shown.

Investigation of Fracture Toughness of Heat Affected Zone of 2.25Cr-1Mo-0.25V Steel Pressure Equipment

2017 ◽  
Author(s):  
Weijie Wu ◽  
Yan Song ◽  
Mengyu Chai ◽  
Zaoxiao Zhang ◽  
Guangxu Cheng
Keyword(s):  
Fracture Toughness ◽  
High Pressure ◽  
Crack Initiation ◽  
Heat Affected Zone ◽  
Welding Current ◽  
Fracture Toughness Test ◽  
Initiation Point ◽  
Fracture Properties ◽  
Toughness Test ◽  
Deformation Work

The 2.25Cr-1Mo-0.25V steel, which has excellent thermal mechanical properties under high pressure and temperature, is widely applied in the pressure equipment. Previous researches show that crack generated in the Heat Affected Zone (HAZ) is one of the main failure mechanisms for the high pressure equipment. Consequently, this work aims at investigating the fracture behavior of HAZ by fracture toughness test. A set of specimens was manufactured with the welding current of 580 A, then, specimens were tempered at 705 °C for 32 h. Along with the fracture toughness test, the fracture properties (e.g. crack initiation, propagation and fracture) of specimens were monitored by acoustic emission (AE). Comparing the AE amplitude of each specimen, the crack initiation point was verified by the first peak of AE result, and the analysis of deformation work at the initiation crack point has also been carried out to investigate fracture properties and the fracture toughness of HAZ of the 2.25Cr-1Mo-0.25V steel. Then the relationship between deformation work and crack length has been studied, and the fracture toughness of HAZ could be obtained. Analyzing the fracture characteristics of experiment process and fracture toughness of HAZ has a significant guidance for the further applications of 2.25Cr-1Mo-0.25V steel.

scholarly journals Influence of Martensitic Islands on Fracture Toughness and Strength of Weld Heat-affected Zone

1993 ◽  
Vol 79 (10) ◽  
pp. 1176-1182 ◽  
Author(s):  
Tetsuya TAGAWA ◽  
Takashi MIYATA ◽  
Syuuji AIHARA ◽  
Kentarou OKAMOTO
Keyword(s):  
Fracture Toughness ◽  
Heat Affected Zone ◽  
Weld Heat

scholarly journals Type I Fracture Toughness Test of Rock-like Materials Based on the Particle Flow Method

2020 ◽  
Vol 2020 ◽  
pp. 1-15
Author(s):  
Ling Yue ◽  
Bangyong Yu ◽  
Chengxi Zhao ◽  
Fei Guo ◽  
Fei Huang
Keyword(s):  
Fracture Toughness ◽  
Loading Rate ◽  
Numerical Test ◽  
Particle Flow ◽  
Type I ◽  
Fracture Toughness Test ◽  
Test Results ◽  
Flow Method ◽  
Group A ◽  
Group B

In order to investigate the feasibility and reliability of the three-dimensional particle flow method in simulating the type I fracture toughness test, four types of numerical samples were established by particle flow code PFC3D: straight crack three-point bending (SC3PB), edge cracked flattened semicircular disc (ECFSD), cracked chevron notched Brazilian disc (CCNBD), and edge cracked flattened ring (ECFR). Three models with different strength parameters (group A, group B, and group C) were established for each type, in which group A parameters are obtained from the concrete model, group B parameters are applied for simulating marble, and group C parameters are for granite. The type I fracture toughness and the failure form of each model are obtained by conducting the numerical test, and the curves of load versus displacement of loading point are recorded. The numerical test results show that, with the same strength parameter, the maximum difference in test results of each specimen type is 0.39 MPa·m1/2. The KIC of ECFR specimen is 0.13–0.28 MPa·m1/2 smaller than that of CCNBD specimen, and the KIC of ECFSD specimen is slightly higher than that of CCNBD sample. The KIC of SC3PB specimen is 0.06–0.21 MPa·m1/2 smaller than that of the CCNBD sample. When the loading rate is less than 0.01 m/s, the effect of loading rate on fracture toughness can be reduced to less than 0.1 MPa·m1/2.

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