bluuebunny/crossref_metadata_2025_split huggingface dataset:
INCEFA-SCALE (Increasing Safety in NPPs by Covering Gaps in Environmental Fatigue Assessment - Focusing on Gaps Between Laboratory Data and Component-Scale)
Authors: Mottershead Kevin , Cicero Roman , McLennan Alec , Courtin Stephan , Huotilainen Caitlin , Cicero Sergio 
Published: October 2021

Abstract
INCEFA-SCALE is a five year project supported by the European Commission HORIZON2020 programme. It is the successor to the INCEFA-PLUS programme that ran from 2015 to 2020. INCEFA-SCALE kicked off in October 2020. The objective is to continue work, advancing the ability to predict lifetimes of Nuclear Plant components when subjected to Environmental Assisted Fatigue loading (EAF).
It has been generally observed by nuclear plant operators that the number of failure events attributable to EAF is fewer than predicted by the current assessment methodologies. It is internationally recognised that a possible contributor to this discrepancy is the transferability of laboratory-scale tests to real nuclear components. EPRI, in the USA, is leading a series of component-scale environmental fatigue tests that are expected to advance data availability significantly; however, the ability to address transferability of laboratory-scale tests to real component geometries and loadings will still be constrained by limited test data. This is the knowledge gap addressed by INCEFA-SCALE. The project strategy will be (1) the development of comprehensive mechanistic understanding developed through detailed examination of test specimens and MatDB data mining, and (2) testing focussed on particular aspects of component-scale cyclic loading. The project will initially survey and understand the vast amount of test data within JRC’s MatDB database (from the predecessor INCEFA-PLUS project, and from other external sources such as USNRC, EPRI, MHI and the AdFaM project). The experimental programme will be specified in the first year and run for three years. Finally, the project will deliver guidance on the use of laboratory-scale data for component-scale applications.
This paper will report progress in agreeing data gaps, mechanistic understanding needs, and testing requirements.
Hydrogen Induced Cracking Damage Estimation and Evaluation
Authors: Subramanian Kannan , Penso Jorge 
Published: October 2021

Abstract
New non-destructive testing (NDT) inspection technology, quantification of damage, and tensile testing, has enabled the assessment of conservatism associated with the hydrogen induced cracking (HIC) damage parameter (DH) currently used in API 579 – 1/ASME Fitness-For-Service (FFS) Part 7. To address HIC damage from an FFS perspective, the general requirements include addressing protection against plastic collapse and protection against cracking. The focus of this body of work is only to address conservatism regarding the protections against plastic collapse. The detrimental effects of HIC damage on plastic collapse is modeled through the DH parameter, currently set at 0.8 or an 80% strength loss in HIC damage material for the Level 2 HIC Assessment Procedure. Original development of the DH parameter was based on tensile testing of HIC damaged material performed in air, where the HIC damage was not sized or quantified, and a 30% margin was added to the maximum measured reduction in tensile strength to get to the 80% strength loss. Modification of the DH parameter is allowed in the Level 3 HIC Assessment Procedure, provided supporting testing data justifying a reduction is also provided with the assessment.
For the tensile testing in air, the quantified HIC damage and tensile testing results are consistent with an 80% strength loss, without an added margin. A rigorous ultrasonic testing inspection using conventional phased array ultrasonic testing (PAUT) and PAUT with full matrix capture using the total focusing method (FMC/TFM) was performed on ex-service SA-212 Grade B material. Locations with service generated HIC damage were extracted and tensile tested in air and in gaseous hydrogen. Examination of the tensile specimen fracture surfaces allowed for quantification of HIC damage associated with final tensile failure. HIC damage measured with NDT was similar to the HIC damage on the fracture surface when characterized using the crack sensitivity ratio (CSR). The hydrogen tensile testing results suggested that for material still charged with hydrogen (not currently explicitly addressed in API 579 – 1/ASME FFS Part 7), the loss in strength may be larger than 80%.
Micro Ultrasonic Knurling Technology Creating High Precision Texture on Sliding Surface in Mechanical System (Fundamental Experiment)
Authors: Aoki Shigeru , Sakai Yasunori , Tanaka Tomohisa 
Published: October 2021

Abstract
Sliding surface in mechanical system is required to move smoothly and stop at target position. Sliding surface can move and stop by applying adequate friction force. It is necessary to develop machining technology to create texture with high precision and efficiency. On the other hand, ultrasonic vibration is used in many manufacturing fields. It is well known that surface roughness is improved and stress is reduced using ultrasonic vibration. In this study, machining technology creating wear resistant texture on large area sliding surface with high precision and efficiency using ultrasonic vibration during knurling is developed. The technology can be applied to the dampers and the base isolation systems for reduction of seismic response of the structures in this paper, the effect of ultrasonic vibration is examined by the fundamental experiment. In some of those devices, friction characteristics are an important factor for controlling their efficiency. In the experiment making a groove on the surface with an indenter using a 2 dimensional table, pressing force and friction force are measured. These forces are reduced using ultrasonic vibration. Pressing experiment making texture on the surface is also made. Deeper and clearer marks are formed using ultrasonic vibration during knurling.
Investigation on Leak Rates in Thin-Walled Structures
Authors: Silber Fabian E. , Stumpfrock Ludwig , Weihe Stefan 
Published: October 2021

Abstract
The results presented here are an experimental investigation of single phase and two-phase flow of water through pin holes and defined slits. The project was performed to extend the database of experimentally determined leak rates at thin-walled components. Test specimens described herein include five pin holes and three different geometries with defined slits and were manufactured with a wall thickness t of approximately 1.2 mm. Leak rate measurement was performed in parameter range with temperatures ranging from 20 °C to 230 °C and a pressure range from 5 to 75 bar. These experiments cover a t/dh ratio range from 1.4 to 12. Furthermore, leak rates with discharge into a water vessel are compared to free discharge into air environment or rather approximately free discharge into a condenser. As a part of these investigations the formation of a metastable fluid phase in the flow regime at the outlet of the apertures was documented with a high-speed camera, evaluated and categorized for different geometries. Within this contribution an overview of the test facility, the testing procedure, and a selection of results of the investigations will be presented and discussed.
Fatigue Behavior and Lifetime Assessment of the Austenitic Stainless Steel AISI 347 and its Associated Filler Metal ER 347 Under Low-, High- and Very High Cycle Fatigue Loadings
Authors: Schopf T. , Weihe S. , Daniel T. , Smaga M. , Beck T. , Rudolph J. 
Published: October 2021

Abstract
The fatigue assessment of safety relevant components is of importance for ageing management with regard to safety and reliability. Those components are subjected to low cycle (LCF), high cycle (HCF), very high cycle fatigue (VHCF) and their combination in terms of complex loading collectives and nonlinear fatigue damage accumulation. Reactor internals, for example, are subjected to thermo-mechanical fatigue induced by operational temperature transients such as stratification loads and to flow induced vibrations. Obviously, methodological gaps within the current fatigue assessment approach, i.e. the assessment of the VHCF behavior, the treatment of the fatigue damage accumulation in combination with the transient endurance limit are to be bridged. Additionally, environmentally assisted fatigue is to be considered properly.
Design fatigue curves in international design codes were extended from originally 106 up to 1011 load cycles. Nevertheless, the existing data base for load cycles above ≈ 107 is still insufficient. The cyclic deformation behavior of the material under discussion (AISI 347 within the recent project and AISI 304 within a follow-up project) is different depending on the fatigue regime respectively to the applied load or deformation amplitude. While the LCF behavior is already well investigated and the basic behavior in the HCF regime is fairly well known the VHCF cyclic deformation behavior has not been characterized so far. As a consequence, the real damage accumulation of variable amplitude combinations consisting of LCF- and HCF/VHCF loads is still widely unknown.
A cooperative R&D project of MPA Stuttgart, WKK University of Kaiserslautern and Framatome GmbH addresses the existing gaps of knowledge discussed above and has recently been finished.
The following topics will be discussed in detail in the paper:
• Basic characterization of the HCF and VHCF behavior at relevant operational temperatures in air at 106 – 2·109 load cycles (base material and welded material)
• Fatigue behavior at variable amplitude loading (combination of LCF / HCF and LCF / VHCF)
• Numerical simulations and fatigue assessment of VHCF-regime loadings
• Development of a fatigue assessment methodology under consideration of the transient endurance limit and damage accumulation effects including assessment and adaptation of appropriate fatigue damage parameters
Demonstration of Intelligent Welding Machine for Polyethylene Pipe
Authors: Xiang Guangte , Hu Yurui , Zeng Sheng , Shi Jianfeng , Zheng Jinyang 
Published: October 2021

Abstract
Electrofusion (EF) welding is one of the most common connection methods for polyethylene (PE) pipe, as well as thermoplastic pipe and reinforced composite pipe. Conventional EF welding generally adopts constant-voltage welding mode. The welding machine outputs a constant welding voltage to heat the resistance wire within specific welding time. In our previous study, intelligent welding machine was designed to ensure the quality of the EF joint, based on the study of the temperature field in EF joint. In this paper, three experiments were used to show the difference between the intelligent welding machine and traditional welding machine. The intelligent welding machine can actively adjust the welding parameters to ensure the quality of EF joint even it was given the wrong welding voltage and welding time. Compared with the traditional welding machine, the intelligent welding machine can automatically control the maximum temperature and the depth of melting region in EF joint during the welding process, and this method applies for EF joints with various diameters or design welding parameters.
Correlating Incident Heat Flux and Source Temperature to Meet ASTM E1529 Requirements for RAM Packaging Components Thermal Testing
Authors: Baird Austin R. , Gill Walt , Mendoza Hector , Figueroa Victor 
Published: October 2021

Abstract
Often in fire resistance testing of packaging vessels and other components, both the heat source temperature and the incident heat flux on a test specimen need to be measured and correlated. Standards such as ASTM E1529 require a specified temperature range from the heat source and a specified heatflux on the surface of the test specimen. There are other standards that have similar requirements. The geometry of the test environment and specimen may make heat flux measurements using traditional instruments (directional flame thermometers (DFTs) and water-cooled radiometers) difficult to implement. Orientation of the test specimen with respect to the thermal environment is also important to ensure that the heat flux on the surface of the test specimen is properly measured. Other important factors in the flux measurement include the thermal mass and surface emissivity of the test specimen. This paper describes the development of a cylindrical calorimeter using water-cooled wide-angle Schmidt-Bolter gauges to measure the incident heat flux for a vessel exposed to a radiant heat source. The calorimeter is designed to be modular to be modular with multiple configurations while meeting emissivity and thermal mass requirements via a variable thermal mass. The results of the incident heat flux and source temperature along with effective/apparent emissivity calculations are discussed.
Case Study of Supplemental Steel Structures
Authors: Wiseman Phillip , Subedi Raju 
Published: October 2021

Abstract
Supplementary steel provides essential connections between building steel or ground to pipe supports and component supports of power and processing plants. This type of structure is usually with steel members less than 10 feet in length and sustains temperature within the range of the ambient conditions and the pipe or component. Being a connection, the standards and Codes provide an array of stress and geometrical checks that share that of a building and of a pressure boundary. Therefore, the applied engineering mechanics utilized in the analysis of supplemental steel configurations, including but not limited to beams, columns, and frames along with their welded or bolted connections, stretches across multiple engineering disciplines. A study of load cases and load case combinations is performed across multiple configurations of assemblies with industry assumptions incorporated. With the mitigation of sag of pipe systems, study of analytical stress and geometrical checks are evaluated to find any correlations of governing criteria. Additionally, the utilization of two types of structural steel design fundamentals and provisions, Allowable Strength Design (ASD) and Load and Resistance Factor Design (LRFD), are investigated with supplemental steel structures which stem from design considerations of steel buildings. This case study in the analysis of supplemental steel structures provides segue to highlighting how Codes and Standards utilized within the field that overlap other fields.
A Comprehensive Review on Failure Analysis of Electrofusion Joint For Plastic Pipes
Authors: Ge Zhoutian , Yao Riwu , Shi Jianfeng , Zheng Jinyang 
Published: October 2021

Abstract
Electrofusion joint plays an important role in connecting plastic pipes and composite pipes. The safety of electrofusion joint has been of major concern affecting the pipeline system. Existing researches reveal that the failure of electrofusion joints is influenced by intrinsic factors such as welding and installation qualities, and external factors such as various load conditions. The combination of these factors would result in different failure modes of electrofusion joints. This paper provided a comprehensive review of current publications on failure analysis of electrofusion joints focusing on both the intrinsic and external factors. The former summarized premature failure of joints caused by incorrect production procedure before service, while the latter addressed the relation between failure modes and load conditions. Key factors affecting the failure modes were subsequently listed. Ultimately, based on current researches and industry hotspots, prospects on the development of electrofusion joint were discussed.
Fire-Induced Pressure Response and Failure of 3013 Containers
Authors: Mendoza Hector , Gill Walter , Baird Austin , Figueroa Victor G. , Hensel Steve , Sanborn Scott 
Published: October 2021

Abstract
Several Department of Energy (DOE) facilities have nuclear or hazardous materials stored in robust, welded, stainless-steel containers with undetermined fire-induced pressure response behaviors. Lack of test data related to fire exposure requires conservative safety analysis assumptions for container response at these facilities. This conservatism can in turn result in the implementation of challenging operational restrictions with costly nuclear safety controls. To help address this issue for sites that store DOE 3013 stainless-steel containers, a series of five tests were undertaken at Sandia National Laboratories. The goal of this test series was to obtain the response behavior for various configurations of the DOE 3013 containers when exposed to various fire conditions. Key parameters measured in the test series included identification of failure-specific characteristics such as pressure, temperature, and leak/burst failure type. This paper describes the development and execution of the test series performed to identify these failure-specific characteristics. Work completed to define the test configurations, payload compositions, thermal insults, and experimental setups are discussed. Test results are presented along with corresponding discussions for each test.
Regulatory Testing and Posttest Analysis of the DPP-3 Type B Shipping Container for NCT and HAC Tests
Authors: Martinez Oscar , Adeniyi Abiodun , Nogradi Paul , Loftin Bradley , Martinez Coleen E. , Van Hoy Blake 
Published: October 2021

Abstract
Safe transportation of radioactive material using appropriately designed, certified packages ensures protection of the public and environment using rigorous system packaging requirements. This protocol was conducted to determine the effects of drop testing on a Type B shipping package (DPP-3) performance per normal and hypothetical accident conditions tests. Preparation, testing, and post-test evaluations of a Type B shipping package tested to 10 Code of Federal Regulations (CFR) 71.71 and 71.73 requirements are presented. Six packages were subjected to free drop, puncture, and thermal tests per 10 CFR 71.73. The posttest helium leak test showed a leak rate &lt; 1 × 10−7 He-cc/sec, indicating that the containment boundary and leak-tight environment were maintained. Statistical analyses were performed to determine changes in package performance. The null hypothesis was that measurements would not change enough from pre- to post-testing to show statistical significance, which would indicate too much variability in package design. A repeated measures t-test was used to analyze drum lid and containment vessel (CV) torques. All six CV lid torques were statistically significant, but only three drum lid torques were statistically significant. Therefore, lid design caused more variability than necessary when subjected to the horizontal-and-cold, vertical-lid-down, and corner-with-lid-up drop tests. A one-way analysis of variance (ANOVA) analyzed package heights and diameters, with results on height indicating four of the six certification test units (CTUs) were statistically significant. Thus, CTU design caused more variability than necessary when subjected to horizontal-hot, horizontal-cold, corner-lid-up, and corner-lid-down tests. One-way ANOVA analysis of diameter indicated that all six CTUs were statistically significant. Thus, CTU design caused more variability than necessary when subjected to all tests. The DPP-3 has been shown to be an acceptable design for transport of radioactive materials, but statistical analysis revealed that package and test design can be improved to reduce variability in performance before and after testing.
A Case Study of a Challenging Coke Drum Skirt Repair: A Through Wall Crack Extended 360 Degrees Around Circumference
Authors: Gao Huidong , Penso Jorge , Dewees David , Chatham Everett 
Published: October 2021

Abstract
An unusual finding of a through wall crack was discovered along the skirt to bottom head weldment. The crack extended nearly 360-degrees along the circumferential weld seam. This flaw resulted in the drum level dropping approximately 2.5 inches onto the skirt resulting in a visible lean of the drum relative to the adjoining support structure.
This paper describes the inspection, engineering analysis, and repair performed after discovery of this challenging situation. Initial inspection included quantitative measurement of the drum displacement and skirt cracking. Engineering analyses included stability analysis of the coke drum, development of a robust and technical viable repair plan, design of a lifting & rigging system to enable repair in the field, controlled deposition welding (CDW) approach, and detailed description of non-destructive examination (NDE) techniques to assure repair quality control. A skirt crack monitoring program and operation cycle optimization were also implemented following the successful repair of the severe cracking along the drum skirt.
High Energy Piping Walkdowns in Compliance With ASME B31.1
Authors: Cohn Marvin J. , Gialdini Robert J. , Nye Osborne B. 
Published: October 2021

Abstract
This paper discusses high energy piping (HEP) system walkdown requirements and guidelines in compliance with the American Society of Mechanical Engineers (ASME) B31.1 Code. Chapter VII states that the Operating Company shall develop and implement a program requiring documentation of piping support readings and recorded piping system displacements. Guidelines for this program are provided in Nonmandatory Appendix V, para. V-7. The Code also requires that the Operating Company shall evaluate the effects of unexpected piping position changes, significant vibrations, and malfunctioning supports on the piping system’s integrity and safety. These requirements and guidelines have been developed for personnel safety and piping system reliability.
The HEP system should be maintained to behave as expected in the original design analysis unless a field change is justified by qualified personnel. The walkdown program should be an integral part of an asset integrity management program, including observations, documentation, evaluations, corrective actions, and countermeasures.
A thorough HEP system walkdown includes more than documented hanger readings. It should include visual assessments of possible sagging pipe, unusual pipe slopes, building structure damage, lagging/insulation damage, locked spring hangers, piping interferences, damaged spring coils, loose/missing support fasteners, unloaded rigid supports, bent struts, insufficient hydraulic fluid in snubbers, detached Teflon strips on sliding supports, and confirmation that the current supports are consistent with the original design specifications. If accessible, it should be confirmed that there are no gaps in the sliding supports.
This paper illustrates that it is now possible to photographically document spring support position indicator readings from distances up to 30 feet (9.1 meters). Photographic documentation provides higher confidence in the position indicator readings and can resolve many visual documentation discrepancies, such as incorrect support readings, readings from opposite position indicator sides, and parallax issues. If accessible, closer inspections may confirm if a spring support is in fact internally bottomed-out or topped-out.
Nonmandatory Appendix V provides recommended hot walkdown and cold walkdown forms. These forms provide additional space for applicable notes. Example photographs of many piping system anomalies and associated documentation are provided in this paper. ASME B31.1 requires that significant displacement variations from the expected design displacements shall be considered to assess the piping system’s integrity.