Measured residual stresses in Type 304 stainless steel piping butt weldments

Shack, W. J.; Ellingson, W. A.

doi:10.2172/5583131

Cited by 4 publications

(6 citation statements)

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“…The use of an axisymmetric model in the FE weld simulation implies that a uniform distribution of residual stresses is expected around the circumference of the sphere-to-nozzle intersection. Circumferential variations in residual stress are known to be important in girth welds of small diameter and thin section [31,32]. This is probably because thin sections provide a limited heat sink to the welding process and because the moving weld torch subtends a signi®cant proportion of the circumference in small diameter components.…”

Section: Finite Element Predictionmentioning

confidence: 99%

Measurement and prediction of residual stresses in thick-section steel welds

Smith

Bouchard

George

2000

The Journal of Strain Analysis for Engineering Design

136

115

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Significant levels of residual stress are developed in the production of thick-section steel welds. Residual stress can be measured by a variety of methods, although few offer the ability to determine the spatial distribution completely through the thickness. This paper summarizes recent developments in the deep-hole method for measuring residual stresses in thick-section welds. Experimental results obtained from a variety of welded steel components are described. The measurement method has also been used to provide validation for finite element simulations of residual stresses in a welded cylinder-to-nozzle stainless steel component. The paper describes the finite element weld analysis and compares the results with measurements obtained from several locations in the complex geometry. Overall, there is good agreement between the predicted and measured distributions of residual stress, but the magnitudes of predicted stress tend to be greater.

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Section: Finite Element Predictionmentioning

confidence: 99%

Measurement and prediction of residual stresses in thick-section steel welds

Smith

Bouchard

George

2000

The Journal of Strain Analysis for Engineering Design

136

115

View full text Add to dashboard Cite

show abstract

“…The calculated stresses are axisymmetric; this is built in to the finite element code. However, experimental results (15) suggest that this is a realistic assumption for this large line.…”

Section: Review Of Relevant Residual Stressesmentioning

confidence: 92%

“…;' 1.0 a: The welding residual stresses in a 24 inch BWR recirculation line have been calculated (16) and experimentally determined (15). They have been found to be axisymmetric.…”

Section: "'mentioning

confidence: 99%

“…For part-through cracks denote the critical depth as ac (=hac). The critical value of ac for a given stress and crack length b is then provided by the expression = M T (2)(3)(4)(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18) where MT for the corresponding b is defined in equation 2-17. If a> ac' a crack instability in the depth direction will occur.…”

Section: Failure Criteriamentioning

confidence: 99%

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Fracture mechanics models developed for piping reliability assessment in light water reactors: piping reliability project

Harris¹,

Lim²,

Dedhia³

et al. 1982

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consists of two major tasks: (1) the development. of fracture mechanics models for assessing the piping reliability in light water reactor plants; and (2) the validation of the models developed in task (1) by comparing the results with real piping failure data observed. The results of task (2) impact the confidence level for the models developed in task (1). This report is only concerned with task (1). Task (2) results are reported in another NUREG report, 11 Piping Reliability Model Validation and Potential Use for Licensing Regulation Development ... The ultimate objective of this pnoject is to provide guidance for nuclear powe.r plant piping design so that high-reliability piping systems can result. The piping reliability model presented in this report covers two major failure modes, namely, fatigue failure ~nd stress corrosion cracking failure. Both have been observed in the piping systems of light water reactor plants~ Various failure mechanisms such as vibratory stresses, residual stresses, seismic stresses, assembly stresses, and operating stresses, attributed to these two failure modes are considered in the model. Initial interior surface flaws are assumed to exist along either the pipe circumferential direction or the longitudinal direction. In-service inspection is also included in the model. In summary_,. this piping reliability model has wide application to piping 5y5tems in nuclea~ powet• plants .

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“…5) were used, however, different upper and lower bounds for the sz distribution were used for each closure‐lid‐weld region. Based on the additional data, ( 9–11 ) the symmetric upper and lower bounds of sz for the outer closure lid was changed from ±0.30 to ±0.214.…”

Section: Stress Corrosion Cracking (Scc)mentioning

confidence: 99%

Waste Package Performance Evaluations for the Proposed High‐Level Nuclear Waste Repository at Yucca Mountain

Mon

Bullard²,

Mehta³

et al. 2004

Risk Analysis

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The evaluation studies of the proposed repository for long-term storage of spent nuclear fuel and high-level nuclear waste at Yucca Mountain, Nevada, are underway. Fulfillment of the requirements for limiting dose to the public, which includes containment of the radioactive waste emplaced in the proposed repository and subsequent slow release of radionuclides from the Engineered Barrier System (EBS) into the geosphere, will rely on a robust waste container design, among other EBS components. Part of the evaluation process involves sensitivity studies aimed at elucidating which model parameters contribute most to the waste package and overlying drip shield degradation characteristics. The model parameters identified for this study include (1) general corrosion rate parameters and (2) stress corrosion cracking (SCC) parameters. Temperature dependence and parameter uncertainty are evaluated for the general corrosion rate model parameters while for the SCC model parameters, uncertainty treatment of stress intensity factor, crack initiation threshold, and manufacturing flaw orientations are evaluated. Based on these evaluations new uncertainty distributions are generated and recommended for future analyses. Also, early waste package failures due to improper heat treatment were added to the waste package degradation model. The results of these investigations indicate that the waste package failure profiles are governed by the manufacturing flaw orientation model parameters.

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Measured residual stresses in Type 304 stainless steel piping butt weldments

Cited by 4 publications

References 0 publications

Measurement and prediction of residual stresses in thick-section steel welds

Measurement and prediction of residual stresses in thick-section steel welds

Fracture mechanics models developed for piping reliability assessment in light water reactors: piping reliability project

Waste Package Performance Evaluations for the Proposed High‐Level Nuclear Waste Repository at Yucca Mountain

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