bluuebunny/crossref_metadata_2025_split huggingface dataset:
Thermal-Structural and Shock Event Evaluations of the Fueling Pellet Injection System for ITER
Authors: Martinez Oscar , Yaski Sumalatha , Smith Sarah , Godsey Kara , Rasmussen David , Lovett Gary 
Published: November 2024

Abstract
The United States is among seven partner nations in a collaborative effort to design, build, and demonstrate fusion’s ability to become a large-scale carbon-free energy source. Each country has its own domestic agencies that contribute directly to the ITER project. US ITER, which is a US Department of Energy Office of Science project managed by Oak Ridge National Laboratory, is developing world-class engineering solutions to the design, construction, and assembly of the burning plasma experiment that can demonstrate the scientific and technological feasibility of fusion. US ITER’s scope includes completing the preliminary and final design, qualifying materials and processes for manufacture and testing, executing manufacturing, and delivering the fueling pellet injection system (FPIS) to the ITER site for assembly. The US-ITER FPIS system is designed to inject cryogenically frozen pellets of deuterium-tritium into the plasma. The FPIS has two main functions: (1) providing a steady supply of deuterium and tritium fuel and (2) mitigating the impact of edge localized modes on the plasma-facing components.
The FPIS will have the capability to reside in three port cells within a tritium second barrier containment cask. Each pellet cask contains three flight tubes linking with penetrations on the torus cryopump housing and vacuum vessel: two for the magnetic high-field side pellet injection and one for the magnetic low-field side pellet injection. This paper presents the results of the thermal-structural analyses of the FPIS flight tube structural components when subjected to various loads such as electromagnetic loads; nuclear heating; and seismic, operational, and dynamic shock events. The resulting temperatures and stresses under combined conditions satisfied the design criteria to ensure the safe and reliable operation of the FPIS flight tubes within the vacuum vessel.
Safety Equivalency Evaluation of 1992 and 2023 Editions of the ASME Boiler and Pressure Vessel Code
Authors: Oland C. Barry , Lower Mark D. 
Published: November 2024

Abstract
Standards published by the American Society of Mechanical Engineers (ASME), including those for the construction of boilers and pressure vessels provided in the Boiler and Pressure Vessel Code (BPVC), are often incorporated into federal safety regulations. When a specific edition of the ASME BPVC, such as the 2015 edition, is incorporated by reference into a federal regulation, compliance with rules in this edition is mandatory. However, compliance is often not possible because new boilers and pressure vessels can be stamped only with the appropriate certification mark that corresponds to the edition of the ASME BPVC in effect when the boiler or pressure vessel was contracted for by the manufacturer.
This paper summarizes the technical rationale and engineering bases for explaining why rule changes to an obsolete edition of the ASME BPVC result in boilers and pressure vessels that are at least as safe as those constructed in accordance with rules specified in the 2023 edition, which is currently in effect. The process used to evaluate equivalent safety is based on a qualitative and quantitative comparative analysis approach in which the safety consequences and potential benefits of a rule change are assessed. Rule changes that result in boilers and pressure vessels with equal or greater safety are considered equivalent.
Environmental Fatigue – Early Results Revisited
Authors: Solin Jussi 
Published: November 2024

Abstract
VTT started in 1999 developing capability to conduct LCF tests in hot water environments and published first EAF results for 316NG in the 3rd Int. Conf. on Fatigue of Reactor Components (Seville 2004) and supplemented by results for titanium stabilized alloy 321 in paper PVP2006-93833.
This paper revisits these 20 years old experiments in aim to put their significance in perspective and to underline relevant findings on different performance of the stabilized and non-stabilized alloys. An interesting difference in secondary hardening was measured: alloy 321 hardens at RT air, but 316 NG rather in hot water. This finding was in line with the GE (Solomon & Amzallag) results at the time and with more recent research.
A warning on misinterpretation of the results is delivered. The tests were properly and reproducibly conducted, but — as most of the EAF facilities — the prototypical EAF devices were not able to provide compliance with the standard LCF test procedure of ASTM E606. The author recommends that the results presented in PVP2006-93833 should not be considered as quantitatively valid fatigue data, but comparison of the material responses within this set should be fine.
Fracture Mechanics Assessment of the Steam-Generator Tubesheet Plate Through a Modified Global Approach to Consider the Geometrical Effect on Fracture
Authors: Ancelet Olivier , Marie Stephane , Chapuliot Stephane , Parrot Aurore 
Published: November 2024

Abstract
Because of the carbon macro-segregation inherent to the large thickness flat component manufacturing, the Fracture Mechanics Assessment (FMA) of the Steam Generator Tube-Sheet (SG-TS) was required for flaws postulated close to the primary (and cladded) surface or the secondary (non-cladded) surface in France.
For those assessments, a flaw relying two holes is postulated, which represents a singular configuration compared to conventional FMA. Indeed the flaw is relatively small in comparison to the plate thickness and the crack length is limited by the distance between two holes. To take benefit of the geometry effect of this configuration, a methodology based on a modified global approach was proposed [1]. Applications of this methodology predict benefits of loss of constraint for several tubesheet configurations as underclad flaw or surface flaw with mechanical or thermomechanical loading. Significant constraint effect for underclad flaw and moderate effect for surface effect are estimated.
To validate the relevance of this approach, two actions are undertaken:
- In the first one, this methodology is applied on an experimental data base which different constraint effect. This data base contains numerous fracture tests performed by both EDF and Framatome on various specimen geometries extracted from a 18MND5 low alloy ferritic steel plate, in the brittle-to-ductile transition regime. C (T), SE(T), SE(B), and non-standard specimens.
- In the second one, this application rule is validated through the interpretation of fracture tests performed in the brittle to ductile transition temperature range of specimen representative of a flaw between two isthmuses.
The results obtained by this application appear accurate, providing very interesting perspectives for the assessment of the SG-TS, but also the assessment of other configurations such as small surface flaws configuration encountering constraint loss (loss of constraint called the small flaw effect).
Residual Stress Modelling in PWR Reactor Pressure Vessel Welded Joints
Authors: Robin Vincent , Breder Teixeira Lucas , Albrecht David , Hendili Sofiane , Hilal Sami , Pereira Alvarez Pablo , Delmas Josselin , Depradeux Lionel , Smith Mike C. , Vasileiou Anastasia 
Published: November 2024

Abstract
Residual stress and strain measurements were performed on a narrow gap weld mock-up consisting of a 130 mm thick low-alloy ferritic steel plate of type SA508 Grade 3 Class 1. A submerged arc welding (SAW) process with two beads per layer [1] was used. The thermal response during welding was recorded to provide information for numerical modelling of heat transfer. Detailed through-thickness measurements of residual stresses were made in the as-welded state using both incremental deep hole drilling and the contour method, and after post-weld heat treatment using deep hole drilling [2].
In this paper, a finite element model of the mockup is described as well as some recent modelling improvements achieved thanks to internal EDF R&D activities and within the framework of NeT Task Group 8 [3]. Comparison between measurements and simulations are in very good agreement. The results presented in this paper are useful for the validation of numerical models for the prediction of residual stress states, including the description of the material behavior which depends on phase fraction evolution and tempering effects. Post-weld heat treatment significantly relieves the welding residual stresses and a focus on its modelling is presented in this paper as it is seen as a key step of the manufacturing operation, reducing the level of residual stresses in reactor pressure vessel’s welded joints.
Experimental Validation of Theoretical Burst Strength Solution for Defect-Free Thick-Walled Pipes
Authors: Zhu Xian-Kui 
Published: November 2024

Abstract
The burst pressure of line pipes is an important strength property required in pipeline design and integrity management. Historically, the Barlow formula in conjunction with the ultimate tensile stress (UTS) of pipeline steels were utilized to estimate the burst strength of line pipes. However, the Barlow formula did not consider the plastic flow effect for ductile steels and is applicable only to thin-walled pipes (D/t ≥ 20). In 2006, this author proposed a new multiaxial plastic yield theory and obtained a theoretical Zhu-Leis solution of burst strength for defect-free thin-walled pipes in term of UTS and strain hardening exponent n of pipeline steels. The Zhu-Leis solution has been validated by various burst test data for thin-walled pipelines for a wide range of steel grades from Grade B to X120. Recently, this author extended the Zhu-Leis theory of plasticity to thick-walled pipes and obtained the Zhu-Leis solution of burst pressure for thick-walled pipes. The proposed burst pressure solution is applicable to both thin and thick-walled pipes.
To experimentally validate the proposed theoretical burst pressure solution, this paper obtains a set of burst test data for three thick-walled pipes in Grade B carbon steel with a nominal diameter of 2.375 inches and three nominal wall thicknesses, resulting in D/t = 15.4, 10.9, 6.9. Through comparisons, these burst data validate the theoretical burst pressure solution for thick-walled pipes. Moreover, two additional burst test datasets collected from literature for thin and thick-walled pipes further validate the proposed burst pressure solution for both thin and thick-walled pipes.
Comparison Between the Performance of Threaded Connections Versus Welded Connections in Pipe-Fitting Assemblies
Authors: Rusnak Cameron R. , Elfass Sherif A. , Rivas Allen J. 
Published: November 2024

Abstract
Fire suppression piping systems play a crucial role in minimizing the impact of unwanted fires. These systems primarily consist of welded or threaded connections at the pipe/fittings interface. While design codes, like the American Society of Mechanical Engineering (ASME) B31J, extensively address stress intensity/flexibility factors and rotational flexibility/stiffness in welded connections, threaded connections receive limited attention. Furthermore, ASME codes do not adequately address the failure modes of threaded fittings and their implications for system performance.
Recent research conducted at the University of Nevada, Reno (UNR) has sought to highlight these differences. The research team at UNR undertook a comprehensive experimental program involving cast iron threaded pipe-fitting assemblies to gain a deeper understanding of their performance. Under this program, 126 full-scale fitting assemblies were tested. The experiments included three fitting types (elbow, tee, and tee reducers), five (5) fitting sizes (1, 1.5, 2, 3, and 4 inches), and three configurations. All assemblies were filled with water and experiments were conducted at an internal operating water pressure of 140 ±5 psi. The experiments revealed three damage states, with leakage at the pipe-fitting interface being the predominant mode for small size fittings. This is typically different from welded connections. This paper discusses the performance of threaded fittings as compared to the published performance of welded fittings. It also discusses the pressing need to generate new stress and flexibility factors to accurately address the performance characteristics of threaded connections.
A Case Study for a Molten Salt Reactor Design
Authors: Rajasekaran Ramesh , Ching Hsu-Kuang , Bankston David , Deleo Francesco 
Published: November 2024

Abstract
The Molten Chloride Reactor Experiment (MCRE) is a pivotal design platform in developing TerraPower’s Molten Chloride Fast Reactor (MCFR) technology to validate some of its physics and operational principles. The Reactor Enclosure System (RXE) is a central component to this endeavour, serving as the primary containment for the reactor’s molten salt fuel and other internal parts. In adherence to the ASME Boiler and Pressure Vessel Code, specifically for Class A Metallic Pressure Boundary Components, the RXE is designed for various failure modes, including the critical assessment of combined creep and fatigue damage. Given the complex nature of the design process and the impracticality of conducting detailed evaluations of creep-fatigue life for each design iteration during the early stages, this study introduces a pragmatic approach. A comprehensive family of curves is generated to efficiently estimate the creep-fatigue life of one of the configurations of the RXE for a specific set of parameters. The first set of curves outlines allowable thickness concerning through-wall temperature difference and maximum wall temperature for three materials earmarked for RXE construction assuming a constant primary stress, for a fixed service life and load cycles. A second set of curves is introduced to elucidate the RXE’s sensitivity to variations in reactor service life and the number of load cycles within the fatigue damage evaluation. These curves, constituting a practical sizing approach, help designers to efficiently estimate the effects of incremental design modifications on creep-fatigue life, obviating the need for repetitive detailed evaluations. This paper delineates the methodology employed in generating both sets of curves, providing a comprehensive insight into the procedures undertaken. Additionally, the results of this work are presented, which will be a valuable contribution to the efficient design and evaluation of the RXE in the context of the MCRE and a similar procedure can be followed for other components.
Review of Shock Chilling Criteria in API 579-1/ASME FFS-1
Authors: Hay Clifford 
Published: November 2024

Abstract
Shock chilling can occur when a liquid or two-phase fluid comes into sudden contact with a warmer metal surface. Within operating facilities, there are multiple applications which warrant consideration, including pressure relief systems and equipment startup in light hydrocarbon services. The current screening criteria in API 579-1/ASME FFS-1 (2021) is based on an 8 ksi (55.2 MPa) limit for the maximum thermal stress occurring on the metal surface. In this study, an analytical method was utilized to determine transient temperature, stress, and crack-driving force profiles through the wall thickness for different cylinder geometries using postulated flaw sizes. Analytical results were compared against finite element models and show good agreement. Discussion is provided regarding the margin associated with the current API 579-1/ASME FFS-1 approach.
Example problem 3.10 of API 579-2/ASME FFS-2 (2009) (which involves assessment of a demethanizer tower in the cold end of an ethylene plant) is revisited using the updated calculation methodology.
Recommended updates to the assessment procedures in API 579-1/ASME FFS-1 are provided.
Nuclear Graphite Irradiated Material Property Normalization, Interpolation, and Extrapolation Approach
Authors: Walker Adam , Caldwell Kevin , Kellner Stuart , Schroeder Anthony 
Published: November 2024

Abstract
Nuclear grade graphite has several physical characteristics that are advantageous for its use in high temperature reactors, including a high scatter cross-section and a low absorption cross-section (high moderating ratio). In addition to the neutronics benefits of graphite as a moderator, nuclear grade graphite has high thermal conductivity combined with adequate structural strength at high temperatures. However, the material properties associated with graphite grades that are candidates for high temperature environments exhibit a strong dependance on fast neutron fluence (E &gt; 0.1 MeV). The material properties of interest are typically available only at discrete temperature and fluence levels, which results in an expensive process to characterize the material properties across a wide range of operating conditions. In addition, this approach may limit the reactor design to operating conditions and parameters established early in the design process. The purpose of this paper is to outline a technique to interpolate available irradiated material property data, within the bounds of the parameters examined in applicable testing programs, and also extrapolate to irradiation temperatures beyond those provided in the available test reports. Implementing this approach would permit a smaller data set to characterize the irradiation induced material property changes than if tabulated test results are directly used to represent the full range of operation. Furthermore, this paper will outline an example of the application of this approach in which the graphite material is exposed to temperatures that may exceed the upper bound temperatures examined in the Advanced Graphite Creep (AGC) testing program.
Prediction Method for Acoustically Induced Vibration of Process Piping Generated by a Restriction Orifice
Authors: Hayashi Itsuro , Maeda Shun , Yamaguchi Kazuya , Izuchi Hisao 
Published: November 2024

Abstract
Acoustically Induced Vibration (AIV) of the piping system downstream of the restriction orifice (RO) could be a concern when a large amount of gas is released in the blowdown system through an RO. The severity of AIV generated by the pressure reducing devices can be evaluated by utilizing the noise prediction method specified in the IEC standard (IEC 60534-8-3), since it is known that the vibration stress caused by AIV is basically proportional to the sound pressure level at the piping surface. Also, it is expected that the sound pressure level generated by the RO would decrease as the number of holes increases under the same process conditions. However, to the best of the authors’ knowledge, the governing parameter to evaluate the sound pressure reduction effect by a multi-hole orifice plate which is applicable to the IEC standard has not been published.
In this study, experimental investigations were conducted to establish a prediction method for acoustic power generated by multi-hole orifices. As a result, the correlation between the number of holes and the valve correction factors for the acoustic efficiency defined in the IEC standard was obtained. It was confirmed that the sound pressure level at the pipe wall could be accurately predicted by using this method. Also, the comparison between the proposed method and the conventional AIV sound power level calculation method by Carucci and Mueller is presented.
Creep Properties of Gas Metal Arc Directed Energy Deposition Austenitic Stainless Steel
Authors: Jang Eun , DeNonno Olivia , Gonzales Juan , Tate Stephen , Klemm-Toole Jonah 
Published: November 2024

Abstract
Gas metal arc directed energy deposition (GMA-DED) has potential for the power generation industry to reduce both time and cost since larger and more complex part geometries can be constructed compared to the typical subtractive methods. The performance of GMA-DED builds can be influenced by the deposition method, resulting microstructure, and formation of defects or secondary phases in the final component. Previous work in the literature evaluated the mechanical properties of GMA-DED builds for a range of austenitic stainless steels, however there is limited data on the high temperature mechanical behavior. This work evaluated the high temperature creep properties of GMA-DED builds constructed with type 316H, 316L, 316LSi, and 16-8-2 stainless steels at 650 °C, 750 °C and 825 °C. The alloy with longest time to rupture for a given stress varied depending on test temperature. Creep damage accumulation at grain boundaries was observed along with grain boundary precipitates which likely aided in damage accumulation. Evaluating the creep properties with the Larson-Miller parameter showed the majority of results fell within the scatter band of creep performance for wrought 316 alloys, indicating the GMA-DED process may be suitable for use in advanced energy systems.
Predicting Pipe Wall Vibration in Frequency Bands With Low Acoustic and Vibration Modal Coincidence
Authors: Mann J. Adin , Eilers Daniel 
Published: November 2024

Abstract
Accurate predictions of pipe wall vibration from internal dynamic fluid excitations are critical for assessment of damage mechanisms such as acoustic induced vibration. A common method to relate the excitation of the pipe wall vibration to the internal acoustic excitation is through relationships between the modes in the fluid and modes in the pipe wall. At coincidence, the transfer of acoustic energy to the pipe structural vibration is most efficient. Because of variations in the pipe dimensions and the internal acoustic field, the methods to predict the transfer of energy from the internal acoustic field to the pipe wall vibration often uses a frequency band averaged relationship. These methods rely on having a sufficient number of modes and a known coupling behavior in the frequency band over which the average is calculated. However, at low frequencies, the modal density can be such that there are few internal acoustic or structural modes which causes fewer modal coincidences between them to define the coupling behavior. Further, with finite length pipe segments, the coincidence may not occur as with an infinite length duct. In such cases, the radiation efficiency in the mode-based approach does not include coincidence and is augmented with a mass law approach. This methodology was implemented in statistical energy analysis methods. The basic formulation along with an example will be given.
Effect of Friction and Gaps on Elastic-Plastic Piping Supports
Authors: Kobayashi Wataru , Otani Akihito , Kai Satoru 
Published: November 2024

Abstract
In this study, we conducted an elastic-plastic analysis of the piping support with the aim of investigating the effects of piping friction and gaps on the elastic-plastic support.
The shape under consideration is a general framework type piping support, with an aspect ratio of 1.2 or higher, where the effect of elastic-plastic behavior is expected, based on JEAC4601. The analysis model uses 3D shell elements and includes a mass element that simulates piping at the center of the supports. Friction on the pipes is considered only in the in-plane direction and is represented by a gap element with zero clearance. Horizontal gaps are represented by nonlinear springs.
The input is controlled by a triangular wave displacement, gradually increasing the displacement amplitude to perform analysis in the elastic-plastic region. The equivalent stiffness specified in JEAC4601 is calculated from the obtained load-displacement curve to determine the damping effect of the piping supports. The influence of these factors on elastic-plastic properties will be confirmed from the differences in the load displacement curve. The effect of reducing seismic response will be investigated based on the obtained damping effect. The reduction of damping effect is caused by the clearance between pipe and support.