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13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023

作者： Daniell, James Kobayashi, Kazuma Bhowmik, Palash Chakraborty, Souvik Alam, Syed Nuclear Engineering and Radiation Science Missouri University of Science and Technology RollaMO United States Reactor Systems Design and Analysis Idaho National Laboratory Idaho United States Department of Applied Mechanics IIT Delhi New Delhi India

ISBN: (纸本)9780894487910

Transfer Learning (TL) is a procedure used for training Neural Networks (NN) by using pretrained models to provide information to a model with a new output. This is achieved by training one model, freezing the initial layers, and adding an aditional output to them. TL aims to reduce the training data requirement of NNs (valuable in nuclear systems), although most reserached applications focus on image processing or phenomena with more data than nuclear systems. This work aims to use similar or constituent phenomena for TL applications. Specifically, thermal expansion of SiC/SiC cladding is used to inform irradiation swelling at high temperatures. Results show that the trained TL model generalizes predictions better than traditional feedforward models, and achieves higher accuracy. Additionally, TL models were able to extrapolate information outside of the original model’s bounds more easily than feedforward modules. This type of work is expected to be used in nuclear systems due to the low data availability and benefit of generalizing outputs. © 2023 American Nuclear Society, Incorporated.

关键词： Swelling

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Research Progress of Metal-Based Shielding Materials for Neutron and Gamma Rays

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Acta Metallurgica Sinica(English Letters) 2021年第12期34卷 1609-1617页

作者： Bin Gan Shichang Liu Zhen He Fucai Chen Haoxuan Niu Jingchang Cheng Bo Tan Bo Yu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China State Key Laboratory of Light Alloy Casting Technology for High-End Equipment Shenyang Research Institute of Foundry Co.Ltd.Shenyang110022China

The radiation generated by nuclear reaction is harmful to human body and equipment,thus the radiation shielding materials that employ the shielding ability from neutron and gamma rays are the best candidates according to application situations and radiation *** this paper,the researches of metal-based neutron and gamma rays or multiple purpose shielding materials are systematically summarized,and the respective and principal problems of these materials with respect to shielding effectiveness and other performances,such as corrosion,mechanical properties,manufacture,etc.,are ***,the prospect of shielding materials is outlined,which suggests that the development of highly efficient and multiply functional radiation shielding materials with good environmental compatibility is one of the future development trends.

关键词： Radiation shielding materials Metal-based Boron-containing shielding materials High density alloys

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A Transformer-Based Time Series Prediction Model with Contrastive Learning for Nuclear Power System State Monitoring

A Transformer-Based Time Series Prediction Model with Contra...

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Prognostics and System Health Management Conference (PHM-Qingdao)

作者： Pengfei Gou Daiwei Zheng Lei Tang Mengjuan Liu School of Information and Software Engineering University of Electronic Science and Technology of China UESTC Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NPIC Chengdu China

ISBN: (数字)9798350354010

ISBN: (纸本)9798350354027

Prognostics and Health Management (PHM) is currently the mainstream solution for the condition monitoring and maintenance of industrial systems. In PHM, the system condition is monitored by monitoring the operational status parameters of the system to diagnose equipment faults, predict the remaining useful life, etc. Utilizing sequential operational status parameters to complete prediction and classification tasks is usually modeled as a time series processing task. Therefore, a high-performance time series prediction model is crucial for PHM. This paper focuses on the use of time series prediction models to achieve the prediction of key state parameters of the nuclear power system. However, there are still some challenges when directly applying existing time series prediction models to industrial systems. First, obtaining operational data on the nuclear power system is relatively difficult, resulting in a small amount of training data, which causes many models to face the risk of insufficient training or overfitting. Second, most of the existing time series prediction models are composed of high- and low-frequency decoupling modules, while the operational data of nuclear power systems often have fewer high-frequency components, making it difficult for many existing SOTA models to achieve good results. In order to address these challenges, we have developed a Transformer-based time series prediction model with contrastive learning for monitoring the status of nuclear power systems. We evaluated the new model on three nuclear power simulation datasets and four power transformer datasets. The experimental results show that the new model's performance is superior to baseline models. We also proved the effectiveness of our improvement through ablation experiments.

关键词： Training Time series analysis Training data Contrastive learning Predictive models Data models Power systems Power transformers Prognostics and health management Monitoring

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Preliminary Development and Validation of Acena Code for Melting and Freezing Behavior Simulation

SSRN

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SSRN 2024年

作者： Lin, Yue Zhang, Dalin Chen, Yutong Zhang, Xisi Deng, Jian Tian, Wenxi Qiu, Suizheng Su, Guanghui Shaanxi Xi’an710049 China Institute of Reactor Engineering Technology China Institute of Atomic Energy Beijing102413 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

Melting and freezing model plays a crucial role in safety analysis for liquid metal fast reactors under core disruptive accidents. Thus, it’s necessary to establish suitable models for accurate prediction of molten materials migration after severe accidents happens. In this study, a kind of melting and freezing model is established in ACENA code. And the ACENA code is used to simulate the freezing behavior of melt and calculated results are compared with experimental results to verify the applicability of the model. According to the comparison it is shown that the simulation results by ACENA code agree well with experimental results. Both the changing trend and final value of penetration depth of melt are consistent with realistic conditions. Besides, the effects of heat exchange on penetration depth are also analyzed. This research contributes to the development of safety analysis tools for liquid metal reactors under severe accidents. © 2024, The Authors. All rights reserved.

关键词： Melting

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Application of optimus in sensitivity analysis of dynamic response of reactor coolant system 27

Application of optimus in sensitivity analysis of dynamic re...

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27th International Congress on Sound and Vibration, ICSV 2021

作者： Yanli, Yuan Xianhui, Ye WenZheng, Zhang Lijuan, Li Zhenyu, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9788378807995

In this paper, the sensitivity of the dynamic response of reactor coolant system to the input parameters is investigated through OPTIMUS integrated platform, taking the stiffness of the dampers which support the steam generator and the main pump in the reactor coolant system as the input variables. OPTIMUS is a kind of software developed by Noesis Solutions Company, by which the multidisciplinary analysis process can be integrated for collaborative optimization design. OPTIMUS allows users to graphically establish workflows in which they define input files, output files, input parameters, output parameters and analysis tools that are needed to be called and the logical relationships between controls in the process. The dynamic response analysis of reactor system is the key process in the mechanical evaluation. With the continuous improvement of seismic design benchmark and reactor design requirements, the problem of structural stress over-limit is becoming more and more prominent, and the repeated iteration of design to evaluation becomes an inevitable trend. It is necessary to examine the sensitivity of the dynamic response to the key design parameters in the reactor system and find out the design parameters which have a great impact on the reactor dynamic response to shorten the design cycle and improve the design efficiency. In this paper, the sensitivity of the output parameters to the input parameters are investigated by OPTIMUS, considering the stiffness of dampers supporting the steam generator and the main pump as the input parameters, taking the supporting loads of the main equipments as the output parameters. Not only can ANSYS simulation calculations be automatically carried out on the OPTIMUS, but also can the output data be disposed automatically and rapidly. The sensitivity analysis results can be used for the determination of design variables in the subsequent optimization analysis. © "Advances in Acoustics, Noise and Vibration - 2021" Proceedings of

关键词： Sensitivity analysis

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Limit load estimation for finite plates with semi-elliptical defects under tensile loading 9

Limit load estimation for finite plates with semi-elliptical...

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9th Global Conference on Materials science and Engineering, CMSE 2020

作者： Shi, K.K. Fu, X.L. Xie, H. Shao, X.J. Tian, J. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

The ASME code allows the designer to circumvent many of the problems arising in design by elastic analysis by performing plastic or limit analysis of the component. Unlike elastic analysis, these analyses take account of the redistribution of stress upon yield. In limit analysis, the calculation of the limit load for finite plate with different semi-elliptical defects is an important stage for mechanical safety evaluation. The elastic compensation technique proposed by Mackenzie can be used to provide the limit load of a structure with a finite element method and aims at producing a suitable stress filed for the lower bound theory. In the present study, it is assumed that the finite plate exists three kinds of semi-elliptical cracks with low aspect ratio a/c (a/c=0.1, 0.5 and 1.0), respectively. The improved elastic compensation technique realized by finite element method is applied in the limit load estimation. At last, the results show that the improved elastic compensation technique can be used to obtain the limit value for the finite plate with different semi-elliptical defects under tensile loading. Moreover, the improved elastic compensation technique can be easily implemented in any finite element method and enables the limit load for any complex structure to be obtained swiftly. © Published under licence by IOP Publishing Ltd.

关键词： Finite element method

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Comparisons of Subgrid-Scale Models for OpenFoam Large- Eddy Simulation 7

Comparisons of Subgrid-Scale Models for OpenFoam Large- Eddy...

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2020 7th International Conference on Computer-Aided design, Manufacturing, Modeling and Simulation, CDMMS 2020

作者： Feng, Zhipeng Qi, Huanhuan Huang, Xuan Liu, Shuai Liu, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

OpenFOAM is a free, open-source software package that can be used for the solutions of computational fluid dynamics and simulation of various fluid flow processes. Nevertheless, OpenFOAM still lacks default settings and a large number of different numerical schemes and turbulent models should be validated. In this paper, the unsteady flow around a cylinder (Re=3900) is calculated by the large eddy simulation of OpenFOAM. The predictions include the drag and lift coefficient, the pressure distribution around the cylinder, the velocity distribution and Reynolds stress distribution in the wake region, as well as the prediction of the recirculation length and separation angle. Thanks to several simulations, these five subgrid-scale (SGS) models are compared and studied: The Smagorinsky SGS model, wall adaptive local eddy visibility SGS model, dynamic SGS model with Lagrangian averaging, dynamic one equation eddy visibility model, one equation eddy visibility model. The numerical results are verified with the published experimental data. © Published under licence by IOP Publishing Ltd.

关键词： Large eddy simulation

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An Ergonomic Analysis of Main Control Room Console in Nuclear Power Plant Based on Jack 5th

An Ergonomic Analysis of Main Control Room Console in Nuclea...

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Li, Yu-Tong Liu, Ming-Ming Huang, Qing-Huai Gao, Nan Liu, Guan-Ron Zhou, Mao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

In the process of human factor design and preliminary verification of the control room console in Nuclear Power Plant, traditional 2D human model design and analysis method is commonly used. However the results turn to be inaccurate and time-consuming. With the help of human simulation tool Jack, quick and precise analysis can be achieved. This paper puts forward the human factor engineering analysis of main control room console in nuclear power plant based on Jack including the visibility, accessibility, and collision detection. By comparing this method with traditional 2D design, conclusion can be drawn that Ergonomic Analysis of main control room console Based on Jack is more comprehensive and accurate, thus largely increasing the design efficiency and quality. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Verification Method and Basic Guarantee of RPS Availability in Nuclear Power Plant 5th

Verification Method and Basic Guarantee of RPS Availability ...

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： He, Xian-Jian Liu, Ming-Ming Zhang, Qing Luo, Xiao-Jun Wen, Jing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

The third generation nuclear power reactor protection system (RPS) based on computer technology, that is, safety DCS system, is designed with large-scale integrated circuits and real-time embedded software, which has the characteristics of complex structure, large system scale and high verification difficulty. In order to ensure the safe operation and economic benefits of nuclear power plants, RPS needs not only reliability and stability, but also high availability. In order to explore the feasibility of verification of DCS availability index, based on Hualong One safety DCS engineering prototype, a set of availability testing methods and basic guarantee conditions suitable for DCS suppliers are summarized for discussion and exchange. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Reliability Verification Scheme for Safety Class DCS and Its Implementation in Nuclear Power Plant 5th

Reliability Verification Scheme for Safety Class DCS and Its...

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5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Liu, Ming-ming Chen, Yang He, Xian-jian Xu, Biao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

System Availability, Rejection rate and Malfunction rate are vital technical indicators for safety class DCS when evaluating the reliability of the control system to meet technical requirements. This trend has attracted great attention of equipment manufacturers, regulatory agencies and users. Since there is no relevant standards or norms to guide the restriction at this stage, there is no unified verification idea in the industry. Although domestic and foreign equipment enterprises have tried relevant verification research, it still remains at the level of theoretical analysis and the confidence is not high. In the research of test method, if the traditional test simulation method is used for index verification, it often requires a lot of manpower, material resources and time. Therefore, this method is also regarded as inoperable, so it has not been able to form a reasonable and mature test of the verification scheme for a long time. Based on the general principle of reliability analysis, this paper makes a comparative analysis of the objects of reliability test, and proposes a reliability analysis verification and implementation scheme of safety class DCS. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Reliability analysis

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