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SSRN 2022年

作者： Zhao, Chen Lou, Lei Zhang, Bin Zhou, Bingyan Peng, Xingjie Wang, Lianjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

design of high-performance lead-based fast reactor has already become a hotspot in the advanced reactor system. Research of the neutronics performance improvement is presented based on the small lead-based fast reactor SLBR-50. Parameter sensitivity analyses are conducted, including height-diameter ratio(H/D), reflector assembly arrangement, pitch-diameter ratio(P/D) in fuel assembly, fuel material and fuel enrichment partition. Numerical results of eigenvalue in burnup procedure, assembly power distribution and energy spectrum are analyzed. These results provide influences of these design parameters in quantity and the neutronics performance can be improved with parameter optimization. © 2022, The Authors. All rights reserved.

关键词： Fast reactors

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Characteristic Analysis of a Cylindrical Linear Motor for Drive Mechanism

Characteristic Analysis of a Cylindrical Linear Motor for Dr...

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International Conference on Electrical Machines and systems (ICEMS)

作者： Xu Niu Tianda Yu Lu Zhang He Zhang School of Electrical Engineering Harbin Institute of Technology Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

The control rod drive mechanism (CRDM) is a critical device in nuclear plants. This paper proposes a kind of CRDM applying the cylindrical linear induction motor (CLIM). First, the structure and the working principle are introduced. Second, the finite-element method (FEM) is applied to analyze the electromagnetic characteristics of CRDM. The lifting force variation curves with different electromagnetic and structural parameters are obtained. Third, the thermal analysis is carried out by FEM. The steady-state thermal distribution and temperature of each component of CRDM are obtained. All the above results show that the proposed CRDM can meet the design criteria and such functions as rising, falling, and holding still.

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POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION for DATA ORIENTED NUCLEAR reactor ACCIDENT DIAGNOSIS system

arXiv

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arXiv 2022年

作者： Li, Chengyuan Li, Meifu Qiu, Zhifang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

During applying data-oriented diagnosis systems to distinguishing the type of and evaluating the severity of nuclear power plant initial events, it is of vital importance to decide which parameters to be used as the system input. However, although several diagnosis systems have already achieved acceptable performance in diagnosis precision and speed, hardly have the researchers discussed the method of monitoring point choosing and its layout. For this reason, redundant measuring data are used to train the diagnostic model, leading to high uncertainty of the classification, extra training time consumption, and higher probability of overfitting while training. In this study, a method of choosing thermal hydraulics parameters of a nuclear power plant is proposed, using the theory of post-hoc interpretability theory in deep learning. At the start, a novel Time-sequential Residual Convolutional Neural Network (TRES-CNN) diagnosis model is introduced to identify the position and hydrodynamic diameter of breaks in LOCA, using 38 parameters manually chosen on HPR1000 empirically. Afterwards, post-hoc interpretability methods are applied to evaluate the attributions of diagnosis model's outputs, deciding which 15 parameters to be more decisive in diagnosing LOCA details. The results show that the TRESCNN based diagnostic model successfully predicts the position and size of breaks in LOCA via selected 15 parameters of HPR1000, with 25% of time consumption while training the model compared the process using total 38 parameters. In addition, the relative diagnostic accuracy error is within 1.5% compared with the model using parameters chosen empirically, which can be regarded as the same amount of diagnostic reliability. Copyright © 2022, The Authors. All rights reserved.

关键词： Nuclear power plants

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Quantitative Calculation of Bubble Pinning to Grain Boundaries in Uo2: A Phase-Field Study

SSRN

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SSRN 2023年

作者： Liu, Wenbo La, Yongxiao Jiang, Yanbo Yun, Di Sun, Zhipeng Department of Nuclear Science and Technology Xi’an Jiaotong University Xi’an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

A phase-field model was established to simulate the pinning effect of fission bubbles on moving grain boundaries (GBs) in UO2 nuclear fuel. It was found that the average velocity of the GB at different positions was obviously different during the movement of the GB with the participation of bubbles. The simulation results also showed that the maximum pinning force of bubbles to the GBs is related to the GB energy and the ratio of bubble diameter to bubble spacing (2r/L). The maximum pinning force decreases with the reduction of the 2r/L, which is consistent with the theoretical analysis results. In addition, the logarithm of the average grain size R has a linear relationship with the logarithm of the bubble volume fraction fv. © 2023, The Authors. All rights reserved.

关键词： Grain boundaries

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A Power Regulation Strategy for Heat Pipe Cooled reactors Based on Deep Learning and Hybrid Data-Driven Optimization Algorithm

SSRN

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SSRN 2023年

作者： Huang, Mengqi Peng, Changhong Du, Zhengyu Liu, Yu School of Nuclear Science and Technology University of Science and Technology of China Anhui Hefei230027 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

Heat pipe cooled reactors are suitable for deployment in remote or isolated areas as reliable small-scale power sources due to their good design characteristics. In order to cope with the real-time changing power demand in a dynamic environment, this study proposes a decision-making strategy for power regulation of heat pipe cooled reactors based on deep learning and hybrid data-driven optimization algorithm, which helps to achieve autonomous safe and efficient control of heat pipe cooled reactors under specific power demand. Firstly, an artificial neural network-based power prediction model for heat pipe cooled reactors is constructed;secondly, an evaluation criterion of power regulation schemes that integrates reactor safety and operational effectiveness is established based on utility theory, and finally, a hybrid data-driven optimization algorithm is proposed, which can quickly discover the power regulation scheme with the best utility under specific power demand. The strategy's effectiveness is verified by taking the power regulation process of the MegaPower heat pipe cooled reactor as an example. The results show that the strategy can make stable, accurate and near-optimal power regulation scheme decisions for arbitrary power demand within 20 seconds. © 2023, The Authors. All rights reserved.

关键词： Decision making

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DeepRank: Test Case Prioritization for Deep Neural Networks 35

DeepRank: Test Case Prioritization for Deep Neural Networks

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35th International Conference on Software Engineering and Knowledge Engineering, SEKE 2023

作者： Li, Wei Zhang, Zhiyi Jian, Yifan Liu, Chen Huang, Zhiqiu Collage of Computer Science and Technology Nanjing University of Aeronautics and Astronautics Nanjing China Collaborative Innovation Center of Novel Software Technology and Industrialization Nanjing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Marxism Yangzhou University Yangzhou China Ministry Key Laboratory for Safety-Critical Software Development and Verification Nanjing University of Aeronautics and Astronautics Nanjing China

Deep neural networks (DNNs) have been widely used in safety-critical fields such as autonomous driving and medical diagnosis. However, DNNs are easily disturbed to make wrong decisions, which may lead to loss of life or property. Therefore, it is vital to test DNN adequately. In practice, to reveal the incorrect behavior of DNN and improve its robustness, testers usually need massive labeled data to test and optimize DNN. However, labeling test inputs to detect the correctness of DNN predictions is an expensive and time-consuming task that even affects the efficiency of DNN testing. To relieve the labeling-cost problem, we propose DeepRank, a test case prioritization technique based on cross-entropy loss. The key idea of DeepRank is that the higher the loss value of a test case relative to the DNN, the more likely it is to be mispredicted and the more conducive it is to improve the robustness of the DNN through retraining. Therefore, the cross-entropy loss value can be used for test case prioritization. We experimentally validate our approach on two datasets and three DNNs models. The experimental results demonstrate that DeepRank is significantly better than existing test case prioritization methods regarding fault-revealing capability and retraining effectiveness. © 2023 Knowledge systems Institute Graduate School. All rights reserved.

关键词： Deep neural networks

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design of Shocks & Vibrations Monitoring system for Long Distance Transportation in Confined Spaces

Design of Shocks & Vibrations Monitoring System for Long Dis...

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2023 China Automation Congress, CAC 2023

作者： Huang, Shiyong Geng, Yuru Han, Yong Gu, Mingfei Nuclear Power Institute of China Chengdu China Nuclear Haichuan Nuclear Technology Co. Ltd Chengdu China School of Network and Communication Engineering Chengdu Technological University Chengdu China Chengdu Vocational & Technical College of Industry Chengdu China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350303759

In real life, many valuable products and highvalue important products are transported in long distances. Shocks and vibrations are caused during transportation, loading and unloading for various reasons. Any shock and vibration exceeding the regulations may cause damage to the transported products. So, it is necessary to monitor and analyze these data of shocks and vibrations scientifically, while considering that some transportation conditions have special requirements for installation space and transportation time. Therefore, an ultra-thin and long-lasting monitoring system has been developed based on MEMS accelerometer technology to measure shocks and vibrations. After series of independent tests and calibration tests conducted by a third party on the product, the results show that it can record and store the threeaxis acceleration, temperature, humidity, pressure, time and other parameters of the transportation process in real time, and complete the preliminary assessment of the transportation status of high-value products. Then engineers can conduct professional analysis of the data to obtain scientific transportation monitoring reports, and provide scientific basis for taking safety prevention and treatment measures for subsequent transportation. © 2023 IEEE.

关键词： Vibration analysis

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Optimized Moderator design and Analysis of a Pin-Type Supercritical Carbon Dioxide reactor Based on RMC 29

Optimized Moderator Design and Analysis of a Pin-Type Superc...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zhao, Xingyu Liu, Minyun Cui, Rongyi Huang, Shanfang Wang, Kan Lu, Chuan Department of Engineering Physics Tsinghua University Beijing China Cnnc Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology Nuclear Power Institute of China Chengdu China China Nuclear Power Engineering Co. Ltd Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886502

This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the YH2 on the coolant void reactivity was studied along with a moderator zoning scheme to flatten the radial power distribution. The YH2 was added as hexagonal moderating rods at the center of the fuel assemblies. The core was modeled using the continuous-energy reactor Monte Carlo code, RMC, with the On-The-Fly cross sections treatment. The results showed that the YH2 moderator increased the thermal fission and reduced the critical enrichment of the core with the same diluent volume fraction by more than 30%. The YH2 moderator significantly softened the neutron energy spectrum and reduced the neutron leakage upon core voiding, resulting in both a weaker positive spectral reactivity feedback and a weaker negative leakage reactivity feedback during core depressurization. For an UO2-loaded core, the YH2 gave a lower negative coolant void reactivity, while for a MOX-loaded core with diluent volume fractions smaller than 35%, the spectral feedback was more important and the YH2 strongly reduced the positive coolant void reactivity to less than $1. Arranging the YH2 in the peripheral assemblies reduced the radial power peaking factor to 1.319. The study shows that the YH2 moderator can reduce the critical enrichment, make the core less sensitive to voiding, and can flatten the radial power distribution of a single-enrichment core through moderator zoning. © 2022 by ASME.

关键词： Carbon dioxide

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Uncertainty Quantification of Spray Nozzle Fatigue Analysis Under Transient Load 1

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作者： Liu, Zhenyu Li, Lijuan Zhang, Liping Li, Hui Shao, Xuejiao Jiang, Lu Zhang, Ying Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Changshun Avenue Chengdu Sichuan610200 China

ISBN: (数字)9783030683030

ISBN: (纸本)9783030683023;9783030683054

In this paper, the randomness concept of input parameters is introduced into the design of nuclear equipment, and the uncertainty analysis of input parameters is carried out for fatigue analysis. Taking the pressurizer spray nozzle as the research object, considering the random fluctuation of temperature and pressure of the transient load, the reliability and distribution of the fatigue usage are obtained by performing fatigue analysis according to the fatigue analysis method of nuclear power equipment with Monte Carlo sampling method. Taking section No.3 as an example, the thermal analysis and stress analysis models are established. Through the parameter sensitivity analysis, the relative sensitivity of the fatigue usage to each input parameter is obtained. From the results, it is clear which parameters have a significant impact on the results. The results can further optimize the structural design of the nuclear power equipment and improve its fatigue resistance, which has great application value to the life extension of nuclear power equipment. © 2021, The Author(s), under exclusive license to Springer Nature Switzerland AG.

关键词： Uncertainty analysis

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Peridynamic Simulation for Thermal and Mechanical Behavior of Manufactured Structures with MIG Welding 1

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作者： Li, Hui Zhang, Liping Liu, Zhenyu Li, Lijuan Zhang, Yixiong Shao, Xuejiao Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Changshun Avenue Chengdu Sichuan610200 China

ISBN: (数字)9783030683030

ISBN: (纸本)9783030683023;9783030683054

A new numerical simulation method is developed for the evaluation of thermal and mechanical analyses of manufactured structures with Metal Inert Gas (MIG) welding on the basis of the peridynamics. The peridynamic formulations of the weak coupled thermo-mechanical problems are derived based on a heat transfer model and a microplastic model. To simulate the MIG welding process, a birth–death material point method in the peridynamic framework is proposed to model the addition of weld metal to the workpiece. To simplify the calculation process and improve the computational efficiency due to no need of updating the neighbourhoods of material points, an additional scalar field is introduced in the equations to describe the birth and death states of the material points. In addition, the present method is applied to simulate a classical model of two plates being joined together by the MIG welding. The results indicate that the residual tensile deformations are formed in the welded area while the residual compressive deformations are formed far from the wild line after the release of the clamps on account of the plastic deformation. These results also demonstrate the validity of the present method for the simulation of the MIG welding by comparing with the reference solution. © 2021, The Author(s), under exclusive license to Springer Nature Switzerland AG.

关键词： Computational efficiency

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