bluuebunny/crossref_metadata_2025_split huggingface dataset:
Technical Revisions of JSME Environmental Fatigue Evaluation Method
Authors: Asada Seiji , Nakamura Takao , Kamaya Masayuki , Takahashi Yukio 
Published: November 2023

Abstract
In Japan, environmental fatigue evaluation for LWR components is required in plant life management (PLM) by the regulator. The utilities are using JSME “Environmental Fatigue Evaluation Method for Nuclear Power Plants” (JSME S NF1). The first publication of JSMS S NF1 was the 2006 Edition, and it was revised in the 2009 Edition. Recently, the Subgroup on Fatigue Evaluation in the JSME Committee on Power Generation Facility Codes has developed three technical items for the JSME Environmental Fatigue Evaluation, and those have been approved by the Committee. Those revisions will be incorporated into 2022 Edition. The first one implements revised design fatigue curves. The second one revises the environmental fatigue life correction factor, Fen for PWR components. The third one is a Flaw Tolerance Approach for environmental fatigue evaluation. In this paper, the above three items are introduced.
Development of a Piping Qualification Methodology and Testing – Proposal Enhancement to ASME BPVC and B31 Certification
Authors: Josodipuro Irawan 
Published: November 2023

Abstract
Piping play important roles in pressurized static systems. In the oil and gas industry, for example, they are used to perform the process function, transmission and distribution. Given the role of piping which is subject to elevated pressure, temperature, and fatal accidents have occurred in the history of piping, it is important that piping end-users feel confident that the piping they procure meet the safety requirements. This paper presents a case study where there have been breakdowns in the qualification of piping being offered by piping suppliers to the industry that did not comply with industry standards which can adversely impact plant operations and personnel safety. The loss of piping supplier credibility is a concern that may rarely occur in mature economies but seem to be more prevalent in countries where qualification standards are either relatively new or nonexistent. To address this issue, the author presents a systematic approach that can be used to ensure that piping supplied to endusers in power, oil and gas industries in emerging countries meet the design requirements and standards they are required to meet. The process used to control the manufacturers begins with a qualification plan which each supplier has to establish its product line. Following compliance with the qualification plan, a criticality matrix is introduced to the manufacturers that classify the criticality of each piping type in the system and the associated qualification program(s) that the manufacturers need to meet. The validation with an established program has shown some merit and could be applied to all manufacturers in emerging countries to ensure consistency. The details of the qualification program used and how the process is evaluated are covered in the body of the paper together with examples of how the process has worked.
Application of Robotic Digital Radiography in Oil & Gas and Refinery Projects
Authors: Sano Teruaki 
Published: November 2023

Abstract
In the Oil and Gas refinery industry, over 300,000 films must be handled in a single mega-sized project. To reduce the workload needed for this film work, robotic digital RT (DR) was used in some cases, instead of film RT. As a result, work efficiency was improved because the RT exposure time for DR is shorter than that needed for film RT and the time-consuming work needed for changing, handling and developing film was eliminated.
Organization and Basis of ASME Section XI, Nonmandatory Appendix Y, “Crack Growth Rate Curves”
Authors: White Glenn , Fuhr Kevin , Udyawar Anees , Scarth Doug , Shim Do Jun 
Published: November 2023

Abstract
Nonmandatory Appendix Y of ASME Section XI presents relationships for fatigue crack growth rates and stress corrosion crack growth rates for austenitic stainless steels, ferritic steels, and nickel alloys for use in analytical evaluations. These crack growth rate equations are needed to predict the crack growth rate for the applicable cracking mechanism, material, and environment. The cracking mechanisms addressed are fatigue in air, fatigue in water environments, stress corrosion cracking, and irradiation-assisted stress corrosion cracking. Boiling water reactor and pressurized water reactor water environments are included. Nonmandatory Appendix Y was introduced within the 2021 Edition of the ASME Boiler and Pressure Vessel Code as a consolidated repository for crack growth rate equations. A second objective of Appendix Y is to standardize the nomenclature, physical units, and figures associated with the various crack growth rate relations. Changes anticipated for the 2023 Edition include moving all crack growth rate provisions from other nonmandatory Section XI appendices (including Nonmandatory Appendices A and C) into Appendix Y. This paper describes the organization of the 2023 Edition of Appendix Y and documents the source of each equation. Also tabulated are the active Section XI Code Cases that include crack growth rate equations, as well as the most recent status of acceptance by the U.S. Nuclear Regulatory Commission.
Multi-Axial Stress Creep Consumption Part I; Testing and Validation of Ex-Service 347 SS
Authors: Suzuki Teppei , Ishizaki Yoichi 
Published: November 2023

Abstract
A cracking damage was found in 347SS flange neck operated at about 520 deg. C after long term operation. In previous report presented in PVP2019-9304, it was well explained by creep damage from FEM analysis using isochronous curve based on API 579/ASME FFS-1 MPC Omega method. Following our previous paper, specimens were obtained from the replaced flange operated for 4 years. Using those specimens, destructive testing and remaining life assessment were performed to validate the analysis.
As a result, specimens from the flange neck showed relatively short rupture life, compared to those from other locations. MPC Omega method along with adjustment factors derived from testing resulted in remaining life of 3.1 to 6.8 × 105 hrs. at average operating condition. In consideration with temperature variation during operation, remaining life is estimated to be 2.6 × 10-5 hrs., indicating 10 % life consumption at the time of taking sample. Life consumption estimated by FEM analysis is rather conservative but is comparable within factor of 2 when average strength is applied for the evaluation.
Since the estimated stress conditions and test conditions are close to 0.2% proof stress of the material at this temperature range, significant primary creep strain was observed in the tests, that can cause some conservativeness in remaining life by the FEM analysis.
While above, Larson Miller Parameter method also adjusted with rupture test data agrees with MPC Omega method on the assumption of uniaxial tension. However, it gives less-conservative life under the multiaxial stress conditions. Effect of multiaxial stress on creep life is more significantly observed in MPC Omega method, especially when stress ratio is higher.
In this part I of two papers, the detail of creep test will be presented and discussed. In part II, current creep temperature limit shown in API579-1/ASME FFS-1 Part 4 Table 4.1 will be discussed and suggest an upgrade of creep temperature criteria based on the multi-axial creep model we learned through studies.
Present Status of the Fractesus Project: Round Robin on Unirradiated Materials
Authors: Bonny G. , Altstadt E. , Arffman P. , Cicero S. , Obermeier F. , Petit T. , Swan H. , Chaouadi R. , Gaganidze E. , Hargitai B. , Kolluri M. , Kopriva R. , Rozsahegyi P. , Serrano M. , Spätig P. , Uytdenhouwen I. , Wilcox H. , Yamamoto M. 
Published: November 2023

Abstract
The present paper provides a summary of an inter-laboratory round robin on the fracture toughness testing and Master Curve application on unirradiated materials. First, a validation exercise was performed on the analysis of a given force-displacement curve. Then, a validation exercise was performed on the application of the Master Curve procedure on a given data set of fracture toughness results. Finally, the preliminary results of the Master Curve application on mini compact tension (MC(T)) specimens by 13 different labs on six different materials (four base materials and two welds) are presented. The validation exercise on fracture toughness data evaluation showed the need for a uniform conversion from front face displacement to load line displacement. The validation exercise on application of the Master Curve approach to obtain the reference temperature proved the equivalence between the T0TEM software and in-house developed softwares. The inter-laboratory round robin showed the equivalence between T0 obtained by MC(T) and larger specimens, except for A533B JRQ and 73W. The reasons for the deviations of A533B JRQ and 73W are under investigation. As a general comment, it can be stated that the results from MC(T) specimens often indicate material inhomogeneity as compared to the result from larger specimens. This is likely the consequence of the small sampling volume of the MC(T) specimens.
Experimental and Numerical Investigations on the Relaxation Behaviour of Power Plant Flange Connections Under Steady State and Transient Conditions
Authors: Kettler Kevin , Klenk Andreas , Weihe Stefan 
Published: November 2023

Abstract
An essential part of today’s power plants are flanges, for example as connection between turbine housings and pipes. Which allows revisions, inspections and maintenance measures. Ongoing changes towards higher amounts of renewable energy sources leading to higher demands in flexibility to counter balance weather-related fluctuations. This flexibility leads to changing load types with more frequent warm and hot starts, causing uncertainties for the design and the determination of maintenance intervals of bolted flange connections.
In this context, results of a recently finished research project and ongoing numerical investigations are presented. Tests on a model of an IP turbine flange under near-to-service loads such as internal pressure and temperature are carried out using a test rig allowing heating on the flange’s inner surface. Concerning different influences on the stress relaxation behavior results are shown for tests with martensitic and nickel-based bolted joints. The total test time of 5000 h for each bolted joint consist of 2000 h under steady state conditions and 3000 h under transient conditions. Comparisons of the results with the martensitic and nickel-based bolted joint show an opposite creep strain distribution in the bolt and flange. In addition, a significant influence of the already existing creep deformation from previous load periods can be observed. Comparative simulations with a modified Graham-Walles creep model are carried out. The results confirm the differences in creep behavior with both bolted joints and reproduce the observed influence of the previous creep deformation.
Effects of Fatigue Parameters on Fatigue Crack Growth Rate of Pipe Steels and Girth Weld
Authors: Park Dong-Yeob , Liang Jie 
Published: November 2023

Abstract
Oil and gas pipeline steels and welds are subjected to a wide variety of cyclic loadings: internal pressure variation, pulsation of gas pressure resulting from the cyclic operation of a reciprocating compressor at a gas compressor station, internal flow-induced vibration resulting from the turbulent flow within the pipe, vortex-induced vibration of a free-spanning section exposed to air (wind) for aboveground pipelines or water for water-crossing pipelines, and cyclic thermal stresses developed by significant changes in temperature due to seasonal changes or changes in operating temperatures. These cyclic loadings are very variable and complex. Considering the fatigue situations, a better understanding of the effects of fatigue test parameters on fatigue behaviors of pipeline steels and welds is required. Hence, in this study, the influences of fatigue test parameters on the Paris law coefficients were studied for pipeline steels and welds. It was analyzed for pipe steels of X65∼X100 and a girth weld of X70. Influences of material strength, crack orientation relative to the pipe axis, and frequency in the range of 1∼30 Hz were insignificant. It was found that the coefficients a1 and b2 of the m-ln(C) relationships linearly relied on the load ratio. The constants (α1, β1, α2, and β2) of these linear relationships between R-ratio and a1 (and b2) were determined for pipe steels.
Fit for Service Evaluation of LDPE Tubular Reactor Tubes Exposed to Severe Decomposition
Authors: Abdul Hamid Ahmad Hassan , Abdul Rahim M. Syukri , Mamat Alias , Mat Ibrahim B. , Kadir Alias 
Published: November 2023

Abstract
The low density polyethylene (LDPE) tubular reactor tube is fabricated from a material with extremely high fatigue strength. During severe runaway decomposition reaction, the decomposing gas rapidly heats up the reactor tube bore surface to a temperature exceeding the austenitizing temperature of the steel (AISI 4333). Subsequent quenching by the incoming colder gas from the opening of the hydraulic safety blow-off valve hardens the bore surface. The fatigue life of the reactor tube can be negatively affected by the presence of the hardened layer. A maximum limit of 2 mm for the depth of hardening is specified in the operating manual for safe operation. A hardness test is conducted on the internal surface cross section of the lens ring (gasket connecting the two high pressure tubes) to establish whether the hardening has exceeded the 2 mm depth as a result of decomposition. Due to differences in chemical composition between the reactor tube and lens ring, a correlation between the depth of hardening of the lens ring and reactor tube is investigated. The remaining life of a reactor tube with a 3.4 mm depth of hardening was predicted through experimental fatigue cyclic test approach. Results of the prediction suggested that the depth of hardening of the tube was close representative of the hardened lens ring, while the experimental cyclic fatigue test suggested that the 3.4 mm hardening depth of tube could endure a significant numbers of pressure cycles before the tube fails (i.e. a through-wall crack that leaks).
How to Qualify Gaskets for Low Stress Flanges
Authors: Phan Cuong , Norman Dale 
Published: November 2023

Abstract
Many applications use cast-iron, glass lined, or fiberglass reinforced plastic (FRP) flanges. These flanges usually have limitations with the amount of clamp load that could be generated for sealing and require special gaskets that have a low seating stress. There are a variety of these gaskets in the market. These seals have typically validated their design through standard testing such as DIN EN 13555, and ASTM F2836-18. However, these standards compress the gaskets many times (10x+) beyond the limited maximum allowable clamping load of these flanges. A concern has been raised regarding if the test method might not be applicable to the real-world conditions, as the gasket stresses are so much higher. By reviewing ASME Section X - Fiber-Reinforced Plastic Pressure Vessels, and ASTM D5421 - Standard Specification for Contact Molded “Fiberglass” (Glass-Fiber-Reinforced Thermosetting Resin) Flanges, we are suggesting a low-stress-gasket leakage test by modifying the standard EN 13555 standard leakage test, by applying 20 percent of the standard loads required in each step, and adjusted the test pressure to the common pressure for FRP flanges, of 10 Bar. The paper will provide end-users with data from the modified test method and show the comparison on the leakage performances as it pertains to low-stress-gasket applications.
3D Metrology Analysis of Structural Damages on Type B Shipping Container Compared to Predicted FEA Results After Completion of NCT and HAC Regulatory Testing
Authors: Nogradi Paul , Martinez Oscar , Adeniyi Abiodun , Lowe Lance , Whittenbarger Ross , Fisher Ryan , McLaurine Austin 
Published: November 2023

Abstract
Packages used to transport Type B quantities of radioactive materials must meet normal conditions of transportation (NCT) and hypothetical accident condition (HAC) requirements as defined in Title 10 of the US Code of Federal Regulations, Part 71.71 and 71.73. Evaluating package designs to these criteria typically involves a combination of analysis and physical testing. These required physical tests include free drop, crush, puncture, penetration, compression, vibration, water spray, water immersion, and thermal tests which result in cumulative structural damages that must be evaluated and measured for comparison with data obtained from modeling and other specified standards.
This paper describes a comparison of the structural dimensions of a Type B package that has undergone a series of NCT and HAC tests to the finite element analysis (FEA) model. Dimensional data of the Type B package test unit (TU) was collected using a high-quality 3D scanner. This scan data was then analyzed in a CAD environment to extract the structural damage dimensions that the package experienced. The scanned data was finally compared to the corresponding structural damaged area predicted from the FEA model.
Results obtained from the comparison of the 3D scanned package to the LS DYNA results showed small differences in the diametric and localized impact dimensions. However, most of the dimensions did not vary significantly. These discrepancies were most likely the result of slight variations in the impact drop angles of the physical NCT and HAC tests, whereas the FEA results were created in a perfect orientation.
Assessment of ASTM A723 Steel for Constructing Impulsively Loaded Vessels
Authors: Gibson Joshem , Mueller Joshua J. , Spernjak Dusan 
Published: November 2023

Abstract
An alternate material for thick, e.g. greater than ∼6 inches (152 mm), non-welded Explosive containment vessels (ECVs) cover forgings was investigated. ECVs are used to partially or fully contain the detonation products of explosives. Uses of ECVs include containment of suspect luggage at airports, bomb disposal, containment of dynamic experiments, and disposal of chemical munitions. The impulsive loading and dynamic response of ECVs necessitates the use of materials with high strength and high toughness to prevent ductile exhaustion and brittle fracture. Design rules for impulsively loaded vessels (ILVs), applicable to ECVs, were introduced into Section VIII, Division 3 of the ASME BPVC Code through Code Case 2564 in 2008. In 2019, the ILV design rules were incorporated into Section VIII, Division 3, and Code Case 2564 was annulled. Section KM-4 of Section VIII, Division 3 includes approved materials for vessel fabrication; however, many of these materials either do not exhibit the requisite mechanical properties for ECV applications or lack corresponding published mechanical testing data necessary for ECV design. Another compounding factor is the new guidance in Section KM-234.1 (ASME BPVC Section VIII, Division 3, 2023), which requires Charpy V-notch (CVN) testing 60 °C (108 °F) below the Minimum Design Metal Temperature (MDMT). For many applications, this will require ECV construction materials to exhibit high toughness at low temperatures. In the present study, ASTM A723 steel forgings have been investigated as a candidate material for ECV construction. Mechanical property data from industrially produced forged disks are presented including full CVN temperature-transition curves and tensile test results. Additionally, insight is provided on the effect of tempering temperature on mechanical properties of A723 Steel.
Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region (Report 3)
Authors: Hojo Kiminobu , Hirota Takatoshi , Nagoshi Yasuto , Fukahori Takuya , Sakima Kimihisa , Ohata Mitsuru , Minami Fumiyoshi 
Published: November 2023

Abstract
In order to predict fracture behavior in the ductile-brittle transition temperature (DBTT) region of a structure with low constraint, a plastic constraint correction coefficient χ was proposed. It was defined as a ratio of KJ of a fracture toughness specimen to KJ of a reactor pressure vessel with a specific flaw shape with the same Weibull stress level, and it was given as a function of a shape factor of the Weibull distribution for the Weibull stress, and Ry, yield strength/ultimate strength. The Weibull stress was calculated based on the original Beremin model even in the DBTT region because no ductile crack initiation was confirmed by the RPV model under the four representative pressurized thermal shock (PTS) transient. The coefficient χ was proposed for a simplified facture evaluation to predict an accurate fracture behavior under pressurized thermal shock. In order to introduce χ to the codes, a simplified structural FE model, a flat plate model, was applied. After confirmation of conservativeness of the flat plate model and unirradiated material on χ, the coefficient χ was prepared for a draft standard of the Japan Welding Engineering Society, which was to be extended to other codes and standards, such as ASME Sec. XI, JSME. A main structure of the draft standard was also shown.
Comprehensive Prediction for Temper Embrittlement of Hydrogenation Reactors in Long-Term Service Condition
Authors: Liu Juanbo , Han Zhiyuan , Kang Haoyuan , Chen Sheng , Song Libin , He Meng 
Published: November 2023

Abstract
As critical pressure vessel equipment, hydrogenation reactors are widely used in the petrochemical industry and coal industry. Temper embrittlement, especially under long-term service conditions, is the most important damage mode for hydrogenation reactors. Currently, temper embrittlement in the API 579 (American) and GB/T 36669.1 standards (China) is correlated with embrittlement sensitive X and J factors based on steeping-cooling experimental data. Obviously, service conditions, including operation pressure, temperature and service time have significant effects on temper embrittlement, which should be further considered in the correlation. Besides, from the physical quantity dimension perspective, the dimensions of current prediction correlations for temper embrittlement are inconsistent. Considering the material properties (X and J factors), dimensional features (wall thickness) and service condition (operation pressure, operation temperature, service time) of reactors, this study systematically collected the actual service data in the literatures to propose a comprehensive prediction correlation for temper embrittlement. The parameters related to temper embrittlement are further correlated with non-dimensional numbers to maintain the consistency of physical dimension. The proposed correlation is validated with engineering experiment data, and the results demonstrate that the prediction correlations agree better with actual situation than previous correlations. This study will facilitate accurate prediction for temper embrittlement of hydrogenation reactors in long-term service condition.