bluuebunny/crossref_metadata_2025_split huggingface dataset:
What Best Correlates to High Temperature Failure: Strain, Stress, Dissipation, or Something Else?
Authors: Hu Tianchen , Messner Mark C. 
Published: November 2023

Abstract
There are many damage models postulated in the literature to describe material failure at high temperatures under mechanical loading. Depending on the model, these failure theories describe creep rupture, fatigue failure, creep-fatigue failure, failure under monotonically increasing stress, or failures under all three types of loading. While there are many variations, often models of this sort fall into three general categories: those predominately governed by stress, those predominately governed by accumulated strain, and those predominately governed by dissipated energy. There is no consensus as to which of these general theories is most accurate, and this debate has a practical consequence on engineering design — the predominate high temperature design and fitness for service codes all use different high temperature damage and failure theories. This paper attempts to quantify which of these types of failure theories is most accurate by using machine learning techniques to (1) remove any dependence on the human-guided selection of a particular mathematical form for the failure theory by replacing the mathematical damage function with a deep neural network and (2) using machine learning feature selection techniques to have the computer automatically deduce which quantities best correlate to failure. We test these techniques against a high-quality dataset for high temperature failure in Alloy 617 which includes complete records of the experimentally measured strain, stress, and temperature as a function of time from the start of the test through the failure of the material. These data include a variety of test types and loading conditions, including tension, creep, fatigue, and creep-fatigue tests. The machine learning models trained in this study could be used to directly predict high temperature material failure, but also can help determine which of the simpler engineering failure theories most accurately correlates to experimental failure of the material.
Technical Basis for Inspection Optimization and Deferral of PWR Steam Generator Component Examinations
Authors: Cofie Nathaniel G. , Dedhia Dilip , Chesworth Scott T. , Shim Do Jun , Grizzi Robert 
Published: November 2023

Abstract
Pressurized water reactor (PWR) steam generator (SG) Class 1 and Class 2 components are required to be inspected every ten years by ASME Code, Section XI. A comprehensive survey of over forty years of examination results showed that no known degradation has occurred in these components. A comprehensive study involving stress analyses and probabilistic and deterministic fracture mechanics analyses indicated that the components are flaw tolerant and determined that the inspection of these components can be deferred beyond the current 10-year requirement without compromising plant safety.
A proposed Code Case has been introduced in ASME Code, Section XI that would allow the inspection of SG components to be deferred to 30 years from the date of the last inspection. Specifically, the Code Case addresses the following ASME Code, Section XI Examination Categories and Item Numbers:
• Class 1, Category B-B, pressure-retaining welds in vessels other than reactor vessels (Item Nos. B2.31, B2.32 and B2.40).
• Class 1, Category B-D, full penetration welded nozzles in vessels (Item No. B3.130).
• Class 2, Category C-A, pressure-retaining welds in pressure vessels (Item Nos. C1.10, C1.20 and C1.30).
• Class 2, Category C-B, pressure-retaining nozzle welds in pressure vessels (Item Nos. C2.21 and C2.22).
The technical bases for the proposed Code Case are provided in three EPRI reports (3002014590, 3002015906 and 3002023713). The first two reports were used by lead plants to request relief from the NRC for a 30-year deferral of the examination of the subject components. After many interactions with the NRC, relief was granted to the lead plants; however, the NRC also identified key parameters that should be considered in future requests. Lessons learned from interactions with the NRC were incorporated into the third report, which specifically addressed the 30-year deferral period with consideration of the key parameters identified by the NRC. This third report was only recently published and has not yet been used by a plant to seek relief for the 30-year deferral.
This paper provides the technical basis for the 30-year deferral of the examination of SG components in support of the proposed Code Case using the results of the evaluations in the three EPRI technical basis documents plus additional evaluations specifically addressing the 30-year deferral and the lessons learned through the Request for Alternative process by the lead plants.
Evaluation of the API 579-1/ASME FFS-1 KSSCCL1 and KSSCCL2 Stress Intensity Factors
Authors: Altstadt Steven , Sarzynski Melanie 
Published: November 2023

Abstract
The API 579-1/ASME FFS-1 2021 Fitness-For-Service stress intensity factor solution for a sphere with a surface crack, 360 Degrees, through-wall fourth order polynomial stress distribution (KSSCCL2) was independently investigated in this work. Axisymmetric, linear elastic finite element models of cracked spheres subjected to various applied stress fields were created and assessed. The objective was to estimate stress intensity factors (K) to evaluate crack-like flaws in spherical geometries using a parametric approach. The results were then used to calibrate the respective influence coefficient values (Gi). The sphere with a surface crack, 360 Degrees, internal pressure (KSSCCL1) uses the same table of influence coefficient values (Gi) and thus the new coefficients are also relevant to the KSSCCL1 scenario. A comparison of the newly calculated influence coefficient values to the existing values shows reasonable agreement for spheres with low ratios of internal radius to wall thickness (Ri/t). However, there is increasing discrepancy as the wall ratio increases, with the large differences predicted at Ri/t = 1000. The new influence coefficient values are recommended as an improvement for fitness for service assessments investigating 360-degree surface flaws in spherical geometries subject to fourth order polynomial through-wall stress fields (KSSCCL2) or internal pressure (KSSCCL1).
Artificial Neural Networks for Predicting Burst Strength of Thick and Thin-Walled Pressure Vessels
Authors: Johnson William R. , Zhu Xian-Kui , Sindelar Robert , Wiersma Bruce 
Published: November 2023

Abstract
The common use of pressure vessels (PVs) and pipelines and the high cost of their failure or overdesign in the oil and gas industry makes predicting their burst pressure critical. However, experimental tests of burst pressure are expensive and finite element analysis (FEA) is time consuming. Artificial neural networks (ANNs) hold the promise of rapid prediction of burst pressure for a wide range of PV materials and geometries, including pipelines with defects such as corrosion. This paper demonstrates ANNs designed and trained to accurately predict the burst pressure of both thick and thin-walled PVs for various strain hardening carbon steels. To accomplish this, we trained single and double hidden layer ANNs on experimental data, augmented with FEA, data of predicted burst pressure to create a larger database. A statistical study of hundreds of models exploring the key hyperparameters provided statistically optimal hyperparameters, resulting in highly accurate ANNs. The results, two ANNs with comparably low prediction error across geometries ranging from 3 &lt; Do/t &lt; 120, demonstrate the first use of ANNs to address both thick and thin-walled PV burst pressure within a single network. This is an important step towards designing ANNs for predicting the burst pressure of PVs and pipelines with defects.
Correct Use of Stainless Steel Bolts for Pressure Vessel Applications
Authors: Shargay Cathleen , Daru Kuntak , Gala Punita , Panchal Anilkumar 
Published: November 2023

Abstract
Stainless steel bolts are sometimes specified for pressure vessel applications which are designed according to ASME Section VIII, Div. 11 or Div. 22. The design of the flanges and bolting falls under ASME B16.53 and B16.474 for standard flanges, and under Mandatory Appendix 2 and Para. 4.16 of Division 1 and Division 2 respectively for designed flanges. Stainless bolts have various grades and classes based on material and heat treatment, and size requirements. If special service requirements apply such as meeting NACE standards for wet sour services (namely NACE MR0175 or MR0103)5,6, it can become impossible to meet both the Code and NACE requirements with stainless steel bolts in many situations.
This paper provides information as follows.
1. The paper incorporates flow charts outlining selection of stainless bolts for flanges on pressure vessel to be constructed according to ASME Section VIII, Divisions 1 and 2.
2. Discusses material test requirements and size limits applicable for each class of stainless bolts used on standard and custom designed flanges.
The paper will help the Code user to select proper grade and type of stainless bolts and avoid non-compliances.
Comparison Between Fracture Mechanics Evaluation Methods in ASME Boiler & Pressure Vessel Code, Section XI and Those in JSME Leak-Before-Break Evaluation Guidelines for Sodium-Cooled Fast Reactors
Authors: Yada Hiroki , Takaya Shigeru , Machida Hideo 
Published: November 2023

Abstract
ASME Boiler and Pressure Vessel Code (BPVC), Section XI, Division 2 provides requirements for protecting passive components that affect reliability of the plant. It generally consists of technology-neutral common requirements, and additional ones for individual reactor types. Currently, an Appendix for sodium-cooled fast reactors (SFRs) is being developed based on Code Case N-875. In the Code Case, continuous leakage monitoring was employed as inspection method for components retaining liquid sodium. It is also important to introduce leak-before-break (LBB) assessment procedures in the Appendix because demonstration of LBB is necessary to show the adequacy of applying continuous leakage monitoring to the component of interest. However, LBB assessment method is not provided in ASME BPVC. On the other hand, recently, LBB assessment guidelines for SFRs has been developed by the Japan Society of Mechanical Engineers (JSME). It could be used to prepare LBB assessment procedures for the Appendix, but it needs to confirm the consistency with ASME BPVC Sec. XI. In this study, fracture evaluation methods for pipes with through-wall flaw are compared between the JSME LBB assessment guidelines and applicable evaluation method in ASME BPVC Sec. XI, Div. 1. There are limit load criteria and failure assessment diagram (FAD) approaches in both of them. Allowable flaw size evaluation methods in limit load criteria are almost same. In FAD approach, some differences exist. The FAD approach in the JSME LBB assessment guidelines is based on the R6 defect assessment procedures option 3 and constructed to be consistent with the Fitness-forservice code for light water reactors in JSME. In this study, fracture evaluation methods related to LBB assessment were compared in preparation for introducing LBB assessment procedures into ASME BPVC Sec. XI, Div. 2. Furthermore, effects of the differences were investigated. As a result, it was shown that there was not any significant difference between them except for the structural factors which need to be determined by considering the consistency with related provisions in individual codes.
Development of a Graphite Irradiation Qualification Plan for the XE-100 Reactor
Authors: Campbell Anne A. , Geringer Josina W. , Schrell Adrian M. , Baylis Samuel , Lucas Timothy , Pappano Peter J. , van Staden Martin 
Published: November 2023

Abstract
The American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III “Rules for Construction of Nuclear Facility Components”, Division 5 “High Temperature Reactors”, Subsection HH “Class SN Nonmetallic Core Components”, Subpart A “Graphite Materials”, has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core. Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties. A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor. Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program. But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C. The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy. This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.
Path Forward: Materials Data Modernization for ASME Codes and Standards in the Artificial Intelligence Era
Authors: Ren Weiju 
Published: November 2023

Abstract
Development of the ASME Materials Properties Database was initiated in the early 2010s to support the ASME Codes and Standards. As information technologies advance at an accelerated pace with the artificial intelligence era on the horizon, the ASME Materials Properties Database must be further modernized from a database to a knowledgebase to ride the wave of digital information revolution and effectively support the ASME Codes and Standards in the new era.
This paper is intended to provide an overview of the ASME Materials Properties Database and discuss a roadmap for its future development to facilitate understanding of and participation from different sectors of the Codes and Standards community. It first reviews the basic concepts of data, information, knowledge, database, and database system; as well as the pros and cons in different types of data management, and then discusses the path forward for a desired evolution of the database into a self-explanatory and machine-readable knowledgebase that is consistent with human cognitive processes for the Codes and Standards development and furthermore provides resources for data processing and analysis to reach an eventual goal of streamlining the Codes and Standards development from the initial inquiry, throughout data submission, analysis, ..., to Codes and Standards rule establishment for final publication.
Fatigue Property Evaluation of Metallic AM Parts and Determination of Design Stress Allowables
Authors: Dong Pingsha , Rawls George , Krentz Tim 
Published: November 2023

Abstract
As additive manufacturing (AM) is being adopted for cost-effectively fabricating metallic parts for safety-critical components subjected to fatigue loading, one of the major challenges has been on how to address structural significance of spatially distributed geometric discontinuities. To address some of the issues for pressure equipment applications, a DOE project was initiated to develop a robust metal AM flaw assessment methodology, aiming to examine the feasibility of extracting fatigue design stress allowable. This study was carried out in conjunction with ASME’s BPTCS/BNCS committee activities with test data both provided by some committee member organizations and resulted from a comprehensive literature search. This paper highlights both the technical approach adopted and major findings to date, including: (1) The master S-N curve (or E-N curve) method adopted by ASME BP&V Div 2 Code seems to provide an effective framework for extracting fatigue design stress allowable for fatigue evaluation for AM components; (2)A cost-effective AM flaw acceptance criterion can be implemented by identifying fatigue-critical locations or hot spots as defined in this study for a set of four typical components. (3) Fitness for Service (FFS) methodologies are shown effective in quantitatively establish flaw acceptance criteria for these hot spot locations.
Impact Test Exemption Temperature Reduction of SA-193 B16 Studs for Cold Climate Installations
Authors: Hioe Yunior , Orth Fabian , Bagnoli Kenneth , Moncayo Sabastian 
Published: November 2023

Abstract
SA-193 B16 studs are more cost effective and more reliable in high temperature equipment applications than B8 studs, however B16 stud applications are currently limited in a significant portion of North American and other places in the world colder climates due to the current −20F (−30C) impact test exemption temperature in ASME Section VIII, B31, and FFS-1. Furthermore, MDMT adjustments are not permitted for studs due to preload [e.g., UCS-66(b)]. ASME BPVC Section VIII Division 1 specifies an impact test exemption temperature for SA-193 B7 of −55F (−48C) for up to 2 ½” (64 mm) studs, whereas SA-193 B16 studs have a higher impact test exemption temperature of −20F (−30C) up to 7” (175 mm) studs.
The similar material and chemical properties of B16 and B7 studs (both SA-193) give reason to believe that both stud types should exhibit similar fracture toughness properties at low temperatures. Two-phase research and testing programs have been running for the past few years. The initial research and testing were performed on one sample material to determine if the MDMT for B16 and B7 studs was similar at low temperatures for small diameters. Part of this feasibility study involved developing impact test transition curves through Charpy impact testing, as well as fracture toughness testing, which will be detailed in this paper.
Then the second part of the program was about statistical sampling with material sourced from around the world.
Finite Element Model Mesh Refinement Effects on Qualification of Nuclear Grade Graphite Components
Authors: Mack Andrea , Hoffman William , Bass Joseph , Windes William 
Published: November 2023

Abstract
The American Society of Mechanical Engineers (ASME) provides the full and simplified design-by-analysis probabilistic assessments for determining acceptance of nuclear grade graphite core components. The assessments can be characterized by three parts: (1) a component stress distribution, often determined by a finite element (FE) model; (2) a Weibull probability density function (pdf) that characterizes the experimental tensile strength distribution; and (3) the postprocessor, which combines the FE model and the Weibull strength distribution in accordance with the full and simplified assessments to determine component acceptance. It is known that the level of mesh refinement in FE models can affect the modeled component’s calculated stress distribution. Depending on the component geometry, the stress distribution may converge with sufficient refinement. It was previously unknown whether the acceptance decision resulting from the full and simplified assessments might change even with sufficient mesh refinement. This study explores that question using experimental strength results for a dog-bone geometry for two graphite grades, IG-110 and PCEA. The simplified assessment has two criteria that must be met, the first limits the combined membrane stress by the allowable stress and the second limits the peak equivalent stress by the allowable stress scaled by the ratio of flexural to tensile strength. In the application of the simplified assessment, convergence of the peak equivalent stress required extreme mesh refinement, however, the acceptance decision was not affected. It is hypothesized that more complex geometries with stress concentrations may present mesh refinement effects on the simplified assessment acceptance decision. Mesh refinement did affect the acceptance decision in the full assessment for the applied pressure loadings in this study. This work suggests component stress distribution convergence is not a sufficient criteria for POF convergence in the full assessment and that mesh refinement should continue until the POF has converged, especially where the resulting POF is bordering the SRC acceptable POF limit.
Suggested Improvements to ASME Code Section XI, Nonmandatory Appendix L Flaw Tolerance Approach
Authors: Scott Alexandria , Udyawar Anees , Coleman Joshua , Glunt Nathan 
Published: November 2023

Abstract
The current requirements in ASME Section XI, 2021 Edition, Nonmandatory Appendix L provide guidance for evaluation of components when fatigue usage limits have been exceeded or fatigue usage is predicted to be of concern. As plants apply for subsequent license renewal (SLR), and in turn, fatigue accumulates on components within the reactor coolant system (RCS), flaw tolerance evaluations based on the guidance in Section XI Appendix L become increasingly necessary to assess fatigue. Through these evaluations and recent discussion during the ASME Section XI Task Group on Appendix L at the ASME Code Meetings, the following improvements to Section XI Appendix L are suggested: 1) add a tiered evaluation process for circumferential flaw shapes by first postulating a 360 degree flaw length and determining acceptability for piping components, before needing to move into the Equivalent Single Crack (ESC) aspect ratio tables that are already provided in Section XI Appendix L, and 2) clarify axial flaw procedures for postulated flaw shape in longitudinal welded seam ferritic pipes and austenitic pipes, as well as axial flaws postulated in seamless ferritic pipes and austenitic pipes (i.e., circumferential welds). This paper provides perspective of the impact of the suggested improvements to ASME Code Section XI Nonmandatory Appendix L flaw tolerance approach.
Draft genome sequence of
Sphingomonas paucimobilis
strain Sph5, isolated from tap water filtration membrane
Authors: Koroli Sara , Buss Kristina , Blain Joy M. , Nakka Gautam Sai , Hong Mina , McLean Robert JC , Plugge Caroline M. , Yang Jiseon 
Published: December 2023

ABSTRACT

Sphingomonadaceae are common membrane colonizers and biofilm formers. As part of our studies on long-term genetic changes in drinking water biofilm species, we report the draft genome sequence of
Sphingomonas
strain Sph5, isolated from a tap water filtration membrane. The isolate was determined as
Sphingomonas paucimobilis
through whole genome sequencing and
de novo
assembly.
Twelve new metagenome-assembled genomes from non-axenic culture of
Griffithsia monilis
(Rhodophyta)
Authors: Rizzieri Yanã C. , Lipari August , Gunn Laura , Li Fay-Wei 
Published: December 2023

ABSTRACT

We report 12 metagenome-assembled genomes from a non-axenic culture of the red alga
Griffithsia monilis
Harvey, some of which are distantly related to publicly available genomes.
Draft genome sequences of three
Carnobacterium maltaromaticum
isolates from two low pH bogs in Denmark
Authors: Tang Taya , Leisner Jørgen J. 
Published: December 2023

ABSTRACT

Carnobacterium maltaromaticum
is a lactic acid bacterium that is widely distributed in the environment, including freshwater. Here, we report the draft genome sequences of three
C. maltaromaticum
isolates from low pH Danish bogs, using the Illumina MiSeq platform.