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Preliminary Study on three-dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor 29

Preliminary Study on Three-Dimensional Characteristics of Mo...

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2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Zhang, Haojie Zheng, Yanhua She, ding Shi, Lei Institute of Nuclear and New Energy Technology Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety Ministry of Education Tsinghua University Beijing China

ISBN: (纸本)9780791886502

the two-dimensional (2d) system analysis codes are usually used to design and analyze the modular pebble-bed High Temperature Gas-cooled Reactors (HTR). However, in some cases, three-dimensional (3d) characteristics, for example the 3d power distribution and temperature distribution due to a part of control rods movement, also need to be concerned. In this paper, based on the 200 MWe Pebble-bed Modular High Temperature gas-cooled Reactor (HTR-PM) design, a 3d system analysis code was used to analyze some three-dimensional characteristics in steady state, as well as the transient process caused by the asymmetric movement of control rods in the side reflectors. Under normal operations of HTR-PM, the control rods are inserted at certain heights and the primary coolant enters the Reactor Pressure Vessel (RPV) from the outer pipe of the coaxial hot gas duct. As a result, the fuel temperature has a relative circumferential deviation of about 1.64% on the outside of the pebble bed, while a very small deviation at the center of the bed. the temperature distribution of RPV is significantly affected by the position of the helium inlet as well. the analysis results showed that, during the transient process caused by the withdrawal of two control rods, the relative circumferential deviation of the fuel particle temperature on the outside of the pebble bed would increase to around 8.47%. However, because of heat conduction in relatively long distance, the movement of the control rods has very little effect on the circumferential temperature deviation of the fuel particles at the center of the bed. these 3d characteristics of HTR under different conditions demonstrate the good applicability of 2d and 3d system codes and will provide support for more accurate safety analyses in the future. © 2022 by ASME.

关键词： Heat conduction

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Neutronic and thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel 29

Neutronic and Thermal-Hydraulic Analyses for an Additive Man...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Han, Wenbin deng, Jian Lu, Qi Chen, Chong Xu, Youyou Zhang, Tao Huang, Shanfang Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886502

Additive manufacturing (AM) is a transformational digital manufacturing technology featured with rapidity, customizability, precision, and economy, which is fundamentally altering the way components are designed and manufactured. AM enables the freedom of design, and makes full use of complexity of geometry which comes for free . Applying AM technology to nuclear industry can yield advanced reactor designs with function and structure matched for the best thermal, hydraulic and mechanical performance. In this work, an AM-informed reactor core design with silicon carbide (SiC) matrix and tri-structural isotropic (TRISO) particle fuel is proposed and analyzed. the core is an integrated 3d-printing SiC bulk with helical cruciform coolant channels, and the UO2-bearing TRISO fuel particles are dispersed in the bulk. A multi-physics analysis framework for irregular geometry is developed to analyze and further optimize the reactor design. the TRISO particle positions are generated with discrete element method (dEM). the Reactor Monte Carlo code (RMC) and the commercial CFd software STAR-CCM+ are used for the neutronic and thermal-hydraulic analyses, respectively. RMC simulates the neutron transport to predict the effective multiplication factor and power distribution. STAR-CCM+ calculates the flow and heat transfer in coolant channels and heat conduction in solid matrix with the power distribution as the heat source. Preliminary results show that the power peaking factor FQ decreases below 1.65, the heat transfer area increases by 30.3% and the fuel peaking temperature decreases by 25 K. the optimized AM-informed design enjoys better neutronic and thermal-hydraulic performance than those with regular geometry. © 2022 by ASME.

关键词： 3d printers

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A PHYSICS-dRIVEN X-RAY IMAGE dATA AUGMENTATION MEthOd FOR AUTOMATEd thREAT dETECTION IN NUCLEAR FACILITY ENTRANCEMENT 29

A PHYSICS-DRIVEN X-RAY IMAGE DATA AUGMENTATION METHOD FOR AU...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Xu, Shuo Chen, Gang Li, Weiwei Xiang, Xincheng Institute of Nuclear and New Energy Technology Tsinghua University China Beijing Key Laboratory of Nuclear Detection Technology Beijing China

ISBN: (纸本)9780791886397

due to the perspective ability of the internal structure of objects, the X-ray security screening system has been used to ensure nuclear security in nuclear facility entrancement. To improve detection efficiency and accuracy, recent work posed a particular interest in automated threat detection algorithms based on deep learning. A significant obstacle to developing high performance of such algorithms is the difficulty of obtaining large labeled training datasets. X-ray image data augmentation strategies based on experimental images have been proposed by other investigators. this paper proposed a physics-driven X-ray image data augmentation method for automated threat detection. Using the 3d modeling software, we can construct threat models and project them into threat images without experiment. According to Lambert-Beer law, the simulation image datasets can be made by exponentially overlaying the threat images on the background images. Considering the energy spectrum and scattering effect, we further process the phantoms and projection images accordingly to be more authentic. We train YOLOv5 architecture on the simulation dataset and test the algorithm on the experimental images. the results show that our approach achieves good performances in automated threat detection with an average recognition accuracy of over 90% and a mAP@0.5 of 82.9%, which is an effective method to increase the X-ray image dataset in both quantity and diversity. Copyright © 2022 by ASME.

关键词： 3d modeling

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thE STUdY of COUPLEd FUEL PERFORMANCE ANALYSIS and NEUTRONICS with COMSOL and RMC 29

THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONIC...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Liu, Zhenhai Qi, Feipeng Zhou, Yi Li, Quan Chen, Ping Chen, Hao Ma, Chao Zhao, Bo Li, Chenxi Science and Technology on Reactor System Design Technology Laboratory Npic Chengdu China

ISBN: (纸本)9780791886366

Predicting fuel behavior in the reactor is a typical multiphysics coupling problem. the traditional fuel performance analysis adopts a decoupling way. To provide a higher fidelity tool for fuel performance simulation, the multi-physics coupling software COMSOL and 3d Monte Carlo neutron transport code RMC are coupled. the fuel rod thermo-mechanical coupling analysis module is constructed in COMSOL. RMC is innovatively wrapped as a component of COMSOL to communicate with the fuel performance module. Grid mapping algorithm is set up using COMSOL's functionality. A carefully designed segregation solver sequence is used to control the coupling process. the fine power distribution calculated by RMC is transferred to COMSOL fuel thermal calculation, and the fuel temperature and the coolant temperature and density calculated by COMSOL are transferred to RMC. In a Picard iterative way, the fuel rod lattice level neutron thermomechanical tight coupling is realized. the coupling is demonstrated in a fuel rod BOL steady state case. the fuel performance analysis is enhanced by the higher fidelity neutron flux solution. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Iterative methods

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Accelerating Point Clouds Classification in dynamic Graph CNN with GPU Tensor Core 29

Accelerating Point Clouds Classification in Dynamic Graph CN...

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29th IEEE international conference on Parallel and distributed Systems, ICPAdS 2023

作者： Huang, Haocheng Li, Yangfan Zhou, Xinlian Hunan University of Science and Technology The School of Computer Science and Engineering Xiangtan China Central South University The School of Computer Science and Engineering Changsha China

ISBN: (纸本)9798350330717

Point clouds play a crucial role in various fields such as robotics, 3d modeling, and autonomous driving. dGCNN, as a representative work in this domain, has exhibited superior performance compared to classic models like PointNet++. Such models often display significant computational demands and encounter notable performance bottlenecks, so how to accelerate their calculations has become a noteworthy issue. Nevertheless, due to the inherent disparities between point cloud tasks and conventional convolution tasks, existing algorithms and architectural paradigms designed for convolution frequently prove to be ill-suited for point clouds, such as Tensor Core (TC). there have been studies focused on reducing dGCNN model complexity to improve computational efficiency, but research specifically tailored to TC acceleration remains relatively limited. therefore, we present an encapsulation module that bridges the computation of model in Torch level with the components of the CUdA backend, introducing TC into dGCNN. It dynamically adjusts parameters and computation flow based on input data and transforms batch computations into streaming computations. Additionally, we propose a new computational organization approach, which involves the restructuring of two critical computation steps within dGCNN: the Get Graph Feature operation and the Conv operation. It significantly enhances the computational speed of these two operations while reducing memory redundancy of tensor data involved in the intermediate processes. In the experiment, our modifications achieve an average acceleration of 1.80X for the Get Graph Feature operation and 1.46X for the Conv operation, all while not compromising result accuracy. © 2023 IEEE.

关键词： Classification Convolution dynamic graph update GPU Neural Networks Point Cloud Tensor Core

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determination of Control Rod Position by Global Optimization Methods 29

Determination of Control Rod Position by Global Optimization...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Qian, Zhang ZhiHong, Liu Jing, Zhao Institute of Nuclear and New Energy Technology Beijing China Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety Ministry of Education Tsinghua University Beijing100084 China

ISBN: (纸本)9780791886502

the method is developed to find the implicit position of the control rod using the flux value shown by the neutron detectors. When using the 3d core physics analysis code CPACT, the detector response of a set of predicted rod positions can be calculated. On a double duel problem, functions can be built to describe the difference between the prediction and the target. Under the frame of the inverse problem, combinatorial optimization methods are operated to renew the prediction of rod positions by iteration to a result with convergence. By such a method, the results are guaranteed to achieve the self-consistent with the physical and thermal field while reaching stable convergence when the forward calculation software has been fully verified to simulate the real case. In the meanwhile, the appropriate computational cost is needed and can be adjusted with time tolerance. So, we have compared several global search algorithms (Genetic Algorithm, Particle Swarm Optimization, and Characteristic Statistic Algorithm) with their performance. We can also get the conclusion that hidden features and intermediate calculation results are important to improve the search efficiency. However, the responses of the detectors to some remote rods are not obvious, which are not easy to determine. All the methods were tested on the numerical calculation examples of a pressurized water reactor case. © 2022 by ASME.

关键词： Combinatorial optimization

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A bi-layered three-dimensional mechanical modeling of the cladding and its creep deformation analysis 29

A bi-layered three-dimensional mechanical modeling of the cl...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Zhang, Ming Li, Jinggang Liu, Xiaohan Nuclear, China Lu, Yong Zhu, Yanan China Nuclear Power Technology Research Institute Co Ltd Shenzhen China

ISBN: (纸本)9780791886366

the cladding of the fuel rod is a cylinder-shaped structure made of Zirconium alloy, which will collapse due to structural creep under the extremely service conditions such as high temperature, high pressure, and high irradiation. the collapse of the cladding results in losing its structure function and threatening the safety of the reactor. Based on the commercial finite element software ABAQUS with its user subroutine CREEP, a bi-layered (coating and matrix material) threedimensional (3d) cylindrical cladding model is established with thermal and irradiation finite creep behavior. the external pressure is assumed to be constant acting on the outer surface. the deformation and the rate of deformation increase with the increasing of the irradiation time in the reactor, which leads to the collapse of the cladding eventually. the initial ovality has a positive effect on the creep deformation. Compared with the single-layered model, the coating of the bi-layered cladding can prevent the Zirconium alloy matrix from excessive creep deformation and thus can protect the cladding. the thicker the coating, the stronger the protective effect from the mechanical point of view. A qualitative case of the cladding creep burst was simulated, and the behavior of the creep burst and creep collapse is similar. the corrosion and oxidation behavior are not considered herein for simplicity. the current bi-layered 3d model can be extended to the structural design, safety analysis, as well as life evaluation of some multi-layered cladding of the accident tolerant fuel (ATF). © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Finite element method

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RESEARCH ON STRUCTURAL OPTIMIZATION technology OF FUEL ASSEMBLY PARTS BASEd ON TOPOLOGY ANd OPTIMAL dESIGN 29

RESEARCH ON STRUCTURAL OPTIMIZATION TECHNOLOGY OF FUEL ASSEM...

引用

2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Fan, Huabin Xu, Shiyin Jia, Huili Shanghai Nuclear Engineering Research and Design Institute Shanghai China State Nuclear Uranium Resource Development Co.Ltd Beijing China

ISBN: (纸本)9780791886472

the top nozzle is an important part of the fuel assembly and is located at the core coolant outlet, which has an important impact on the uniformity of the coolant flow distribution at the core outlet and the overall pressure drop of the fuel assembly[1]. the peak stress of the top nozzle under each working condition appears at the position of the adapter plate, top nozzle and the pressure drop of the top nozzle is closely related to the flow area, height and local characteristics of the adapter plate. In this paper, the overall structure of the adapter plate is optimized to reduce the pressure drop as much as possible on the premise of ensuring that the stress meets the requirements of the standard limit. the 3d modeling software NX is used to establish the geometric model of the top nozzle, and it is transferred to ANSYS to establish a finite element model for simulation optimization design. On this basis, the key dimension parameters of the adapter plate (such as the thickness of the rib, etc.) are selected as design variables, and the law of its influence on the blocking area and stress is studied, and the structure size is further optimized. Copyright © 2022 by ASME.

关键词： Pressure drop

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Research and Application of Automatic Modeling technology for Mechanical Analysis of Nuclear Power Pipelines Based on Peps 29

Research and Application of Automatic Modeling Technology fo...

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2022 29th international conference on Nuclear Engineering, ICONE 2022

作者： Gong, Xiaocheng Jin, Xianjing Zhang, Yu China Nuclear Power Engineering Co. Ltd. Guangdong Prov Shenzhen518172 China

ISBN: (纸本)9780791886472

Mechanical analysis of nuclear power pipeline is an important part of nuclear power design. At present, the widely used nuclear-grade pipeline mechanical analysis software in the world is PepS, which almost contains the commonly used standards and specifications in the nuclear power industry. PepS software is used to carry out the mechanical analysis of nuclear-grade pipeline. the key step is building a calculation input pipeline model that accounts for more than 70% of the entire pipe mechanical analysis workload. At the same time, in order to meet the strict process layout requirements of nuclear power, a pipeline usually needs to undergo multiple mechanical analysis and demonstration. there are thousands of pipelines in nuclear power projects, and its mechanical analysis needs to invest a lot of manpower cost. this research deeply analyzes the procedures and principles of PepS calculation input model, the topological structure and geometric characteristics of the 3d model of the pipeline based on the three-dimensional layout design results, and realizes the automatic modeling technology of mechanical calculation input model of nuclear power pipeline based on PepS software through digital and intelligent information technology. the implementation of this technology completely replaces the manual modeling, eliminates the human error of manual modeling, fundamentally liberates the productivity, obtains remarkable economic benefits, and helps the nuclear power design company go hand in hand with multiple projects to realize batch quantitative design and production. Copyright © 2022 by ASME.

关键词： Nuclear energy

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Matching Buildings between 2.5d Maps and dash Cam Images for Building Identification 21

Matching Buildings between 2.5D Maps and Dash Cam Images for...

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29th acm SIGSPATIAL international conference on Advances in Geographic Information Systems, SIGSPATIAL 2021

作者： Awano, Yuki Nishimura, Takuya Ntt Data Corporation Tokyo Japan

ISBN: (纸本)9781450386647

technology that matches buildings between dash cam images and digital maps (GPS) assists in the identification of buildings. the identification enables to collect city information as well as the textures for 3d building models. However, the matching technology has two challenges. First, GPS locations can be highly inaccurate in cities that have tall buildings, which means the GPS sometimes needs to be relocated to capture the correct building features for matching. Second, it can be tricky to set the position and orientation of the camera by making correspondence of certain features of buildings in images and maps. In this work, we propose a method of matching buildings in dash cam images and 2.5d maps that uses the height information of the buildings equivalent to the Lod1 in the CityGML format. For the first challenge, we relocated GPS locations by using a map-matching method. For the second challenge, we adjust positions and orientations by matching the building edges in the images and maps after extracting the edges with a deep-learning-based detection model. Tests using real-world datasets demonstrated that our proposed method matched the buildings better than the baseline. © 2021 Owner/Author.

关键词： Edge detection

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