Piping benchmark problems. Volume 1. Dynamic analysis uniform support motion response spectrum method

Bezler, P.; Hartzman, M.; Reich, M.

doi:10.2172/6403318

Cited by 3 publications

(6 citation statements)

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“…In this section, the TMD optimal design approach for the piping system subjected to seismic loads introduced in this study was applied to the NUREG/CR-1677 benchmark piping system presented by Bezler et al [31]. Additionally, the related results are compared and analyzed according to the TMD optimum design formula and methods.…”

Section: Resultsmentioning

confidence: 99%

“…Material properties and modeling information for NUREG/CR-1677 Benchmark piping system. earthquake load introduced in this section was applied to the benchmark piping system presented in NUREG/CR-1677 [31]. Basically, the seismic responses of the piping systems with/without TMDs were compared and analyzed.…”

Section: Resultsmentioning

confidence: 99%

“…Because the numerical analysis utilizes the frequency response analysis, the numerical inefficiency problem of numerical optimization based on the direct seismic response analysis can be improved. In the following section, the TMD optimal design process approach for the piping system subjected to the earthquake load introduced in this section was applied to the benchmark piping system presented in NUREG/CR-1677 [31]. Basically, the seismic responses of the piping systems with/without TMDs were compared and analyzed.…”

Section: Tmd Optimal Design Approach For a Piping Systemmentioning

confidence: 99%

“…To begin with, the mode analysis of the target piping system was performed according to the TMD optimal design approach for the piping system subjected to the seismic load mentioned in Section 2.2. In this study, numerical analysis was performed in the ANSYS framework; thus, the target piping system defined above was modeled using ANSYS (see Figure 1), and such, the model was verified by comparing with the original mode analysis results (Bezler et al [31]). One of the major contributions of this paper is the use of TMDs for upgrading the seismic performance of piping systems of nuclear power plants.…”

Section: Tmd Optimal Design For the Nureg/cr-1677 Benchmark Piping Symentioning

confidence: 99%

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Enhancement in the Seismic Performance of a Nuclear Piping System using Multiple Tuned Mass Dampers

et al. 2019

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In a nuclear power plant, it is essential to improve the seismic safety of the piping system for the coolant transfer to cool the high temperature caused by the nuclear reaction. Under this background, this study makes two major contributions. The first is that though tuned mass dampers (TMDs) were originally used only to reduce the vibration of piping itself, through this research, it was first proved that it had a positive effect on the improvement of the seismic performance of nuclear piping systems. Additionally, this study proposed a design approach that effectively obtains the optimal design values of TMDs associated with seismic performance. In order to effectively derive the TMD optimum design values, we not only utilized the existing TMD optimum design formula, but also additionally proposed a frequency response analysis-based TMD optimal design method. As a result, it was seen that primary responses of system were significantly reduced under the input seismic load due to the use of TMDs for the piping system. It was also confirmed that the use of the existing TMD formula brought about a similar degree of response reduction effect, while it was possible to get the improved effect when using the proposed method.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Tmd Optimal Design Approach For a Piping Systemmentioning

confidence: 99%

Section: Tmd Optimal Design For the Nureg/cr-1677 Benchmark Piping Symentioning

confidence: 99%

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Enhancement in the Seismic Performance of a Nuclear Piping System using Multiple Tuned Mass Dampers

et al. 2019

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“…次元配管系モデルを図 6 (A ライン) と図 7 (B ライン) に示す． A ラインは NRC レポート(Bezler et al, 1985)の多入力配管系のベンチマーク問題から引用した配管系である．B ラインは同じく NRC レポート (Morante and Wang, 1999)から引用したものであり，米国において多入力を受ける配管系の応答合成法の検討にも使用された配管系である(Subudhi et al, 1984) ．支持点からの励振力としては，図 2 に示す建屋床面における応答加速度の時刻歴波形と図 3 に示す床応答曲線を用い，X 方向に入力した．多入力解析においては，図 6 に示すように，A ラインにおいて節点番号 16 番より上部の節点に設けられるサポートには SG の励振力，節点番号 36 に設けられるサポートには PCCV の励振力，およびその他のサポートには IC の励振力を入力した．また，図 7 に示すように，B ラインにおいて，節点番号 18 番より-X 方向に位置する節点に設けられるサポートには PSB の励振力，節点番号 31 番に設けられるサポートには…”

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Floor response spectrum method of multiply supported piping system assisted by time history analysis

Takayama¹,

Yoshida²,

Iriki

et al. 2020

Transactions of the JSME (In Japanese)

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The uniform support motion (USM) method is generally used for multiply supported nuclear piping system. This method uses a uniform response spectrum (URS) which envelopes all of the individual response spectra and can result in considerable overestimation of seismic responses. An alternate method is the independent support motion (ISM) approach. This approach can also result in overestimation when the maximum responses by multiple excitations are combined by the absolute sum rule, while this may result in underestimation when the maximum responses by the multiple excitations are combined by the square root of sum of squares rule. Then authors have developed a new method of the ISM approach named SATH (Spectrum Method Assisted by Time History Analysis) to achieve a more realistic combination of the maximum responses by the multiple excitations. In the SATH method, both of floor response spectra and floor acceleration time histories are used as seismic input data. The maximum modal responses by the multiple excitations are combined with the effect of correlation coefficients. In order to account for the correlation coefficients, the time history analysis of an oscillator having each of modal frequencies of the piping system is performed using each of the floor acceleration time histories. The correlation coefficients are calculated from the covariance and the standard deviations of time history responses of the oscillators. In this paper, the necessity of taking the effects of the correlation coefficients into account in the ISM approach is discussed, and then the advantage and the applicability of the SATH method to an actual design is confirmed.

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Feature Extraction for Uncertainty Quantification and Reduction of Noise in Condition Monitoring Using Deep Learning

Sandhu,

Bodda,

Sauers

et al. 2023

5th International Conference on Uncertainty Quantification in Computational Sciences and Engineering

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The condition monitoring of structural and mechanical systems in an industrial facility is an important component of digital maintenance platforms. In a nuclear power plant, the structures, systems, and components are continuously monitored as a part of current maintenance procedures. Real-time sensor data collected from systems such as piping-equipment is fed into online condition monitoring programs. Deep learning algorithms such as neural networks can be used as powerful data-based engines to predict damage or aging in pipingequipment systems of nuclear power plants. Factors such as the quality and quantity of data available for training the deep learning algorithm can affect the performance of the condition monitoring framework. Typically, the computational efficiency of deep learning approaches is enhanced by utilizing signal processing and feature extraction techniques on data obtained from sensors installed on the system. This paper presentes a novel feature extraction methodology to quantify uncertainty in the acquired sensor data for the condition monitoring of nuclear piping-equipment systems. Uncertainty in the severity of degradation is classified as minor, moderate, and severe. Signal processing and feature extraction are implemented to calculate a vector of degradation-sensitive elements of interest and reduce the effect of noise in the data. Artificial neural networks are designed and trained using the extracted vector from the sensor response. The condition monitoring framework is tested on various nuclear piping-equipment configurations as well as load combinations.

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Piping benchmark problems. Volume 1. Dynamic analysis uniform support motion response spectrum method

Cited by 3 publications

References 0 publications

Enhancement in the Seismic Performance of a Nuclear Piping System using Multiple Tuned Mass Dampers

Enhancement in the Seismic Performance of a Nuclear Piping System using Multiple Tuned Mass Dampers

Floor response spectrum method of multiply supported piping system assisted by time history analysis

Feature Extraction for Uncertainty Quantification and Reduction of Noise in Condition Monitoring Using Deep Learning

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