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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Yun, Yu Jian, Sun Liu, Hongchun Pan, Zhu Zhou, Jixiang Qi, Ye Science and Technology on Reactor Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

reactor coolant temperature control plays a central role among all reactor control systems because the effect of temperature control is directly related to the load tracking capability and also to the reactor protection margins, such as the over-temperature and over-power restraints. Special for the Mode-A reactor, the capacity of reactor is depending on the accurate and quality of temperature control. For example, in most of the time, all the Mode-A reactors in China are operating at basic load, so the temperature control is always worked in an simple way. But the temperature control system must also consider the quicker response and capacity to the wide range change of load, this paper based on point-kinetic model and heat transfer model in reactor, designs a suitable temperature model for control system. Considering that the traditional PID control method is difficult to solve the robustness and stability of high-order systems for large range operation, this paper uses Multi-model Predictive Control to solve this problem. According to the mechanism model, and establish nine single models, this paper online calculation model -matching degree to get recursive bayesian probability weighting, then get global prediction model. According to the global model, design Multi-model predictive control strategy. The simulation results indicate that under large conditions change, also robust and stable control performance is obtained. Copyright © 2018-2019 by JSME

关键词： Model predictive control

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On Corrosion of Zirconium Alloy in Dissolved Oxygen Water：The Role of Cu Addition

SSRN

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SSRN 2023年

作者： Huang, Zongwen Liu, Qingdong Zheng, Fengxin Peng, Jianchao Yu, Yixiao Zeng, Qifeng Li, Qiang Zhao, Yi Institute of Materials Shanghai University Shanghai200072 China School of Material Science and Engineering Shanghai Jiao Tong University Shanghai200240 China Laboratory for Microstructures Shanghai University Shanghai200444 China Shanghai Nuclear Engineering Research & Design Institute Co. Ltd Shanghai200233 China Science and Technology on Reactor Fuel and Materials Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

It is of significantly important to improve the corrosion resistance of Zr-Sn-Nb alloys in dissolved oxygen (DO) high temperature water by compositional modification. Here, the effect of Cu addition on the corrosion behaviors of Zr-0.5Sn-0.2Nb-0.4Fe-0.2Cr alloy was studied by using an autoclave circulating water loop at 360℃/20MPa up to 250 days. The oxide microstructures were characterized by a combination of SEM, TEM, STEM-EELS and PED. The results showed that compared with 0Cu alloy and 0.07Cu alloy, 0.13Cu alloy shows better corrosion resistance and its final weight gain after 250 days exposure is even lower than that of commercial Zr-4 alloy. The oxides for 0.07Cu and 0.13Cu alloys are more orderly arranged and thinner with less lateral cracks, and the columnar grains show a stronger {10-3} texture, than the Cu-free counterpart. The t-Zr2Cu SPPs have oxidized in the oxygen-rich layer below the O/M interface. The Cu ions tend to diffuse towards the grain boundary of dense columnar grains and maybe strengthen the grain boundaries, avoiding the defect generation under intrinsic stress in the oxide. © 2023, The Authors. All rights reserved.

关键词： Copper corrosion

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Hydrogen risk analysis of a large pressurized water reactor using hydragon code 27

Hydrogen risk analysis of a large pressurized water reactor ...

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Zhang, Xiaolong Yu, Jiyang Huang, Tao Jiang, Guangming Zou, Zhiqiang Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888983051

This paper presents the hydrogen risk analysis of a large Pressurized Water reactor (PWR) undergoing a severe accident using the HYDRAGON code. The code has been developed by the Department of Engineering Physics, Tsinghua University, as a hydrogen risk analysis software specialized for containment building of nuclear reactor power plants. The chemical interaction between zirconium cladding of the fuel rods and overheated coolant may release hydrogen when severe accidents occur in PWRs. The hydrogen mixed with air existing in containment may jeopardize the integrity of containment building if the flammable mixture explodes. In order to mitigate the hydrogen risk, many nuclear power plants install the Passive Autocatalytic Recombiners (PARs) that allow hydrogen and oxygen react chemically at low temperature without any sights of flame. Recombiners remove hydrogen and thereby prevent explosions. This work simulated the gas diffusion behaviors during the accident in the containment of a large PWR. The simulations obtained spatial concentration distribution of various gas species including hydrogen, oxygen, steam and nitrogen and several key parameters that are required to complete hydrogen burning and explosion investigation. Sensitivity analyses of recombiners' quantity and positions and hydrogen discharge intensity provides the reference for hydrogen mitigation measure design in the containment. The results demonstrate that the number of recombiners rather than positions has stronger influences on hydrogen mitigation. Since the installation position reflects less sensitivity, the recombiners could be arranged as higher as possible if necessary. Copyright © 2018-2019 by JSME

关键词： Hydrogen

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CHAINS:CHAIN-based fusion safety system framework for intelligent connected vehicle

Chain

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Chain 2024年第1期1卷 2-45页

作者： Shichun Yang Bin Sun Haoran Guang Rui Wang Bowen Zheng Weifeng Gong Yu Wang Yi Shi Zexiang Tong Lisheng Zhang Kaiyi Yang Xinhua Liu Yaoguang Cao Jun Li Yunpeng Wang School of Transportation Science and Engineering Beihang UniversityBeijing 100091China Innovation Center of New Energy Vehicle Digital Supervision Technology and Application for State Market Regulation Beijing 100091China Imperial College London Ringgold standard institution-Dyson School of Design Engineering London SW72AZUK Research Institute for Frontier Science Beihang UniversityBeijing 100091China State Key Lab of Intelligent Transportation System Beijing 100091China School of Vehicle and Mobility Tsinghua UniversityBeijing 100084China

Intelligent connected vehicles,as the focus of the global automotive industry,are currently at a critical stage of large-scale ***,during the development process of vehicles from mechanical systems with limited functions to mobile intelligence with complex and multiple functions,the issues of functional safety,cybersecurity,and safety of the intended functionality are the main challenges of the industrialization of intelligent connected vehicles,including multiple safety risks such as hardware and software failures,insufficient performance in edge scenarios,cyber-attacks and data *** this paper,the safety and security issues of intelligent connected vehicles,the challenges posed by emerging technology applications,and related solutions are systematically reviewed and summarized.A fusion safety system framework with the safety cube as the core of protection and control is proposed innovatively based on a field-vehicle-human safety interactional model,realizing stereoscopic,deep,and comprehensive safety protection through end-cloud ***,an X-shaped fusion safety development process based on CHAIN is *** the empowerment of digital twin and AI technologies,it could approach interaction between physical entities and digital twin models and the automation of the development process,thereby satisfying the demands of fusion safety system design,intelligent development,rapid delivery,and continuous *** fusion safety system framework and X-shaped development process proposed in this paper can provide important insight into intelligent transportation vehicles and systems'safety and security design and development.

关键词： CHAIN fusion safety X-shaped development process safety brain

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Research about the influence of passive residual heat removal system on SGTR accident 27

Research about the influence of passive residual heat remova...

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Wu, Yirui Shan, Jianqiang Xu, Tao Ma, Haifu Yang, Junyun Yu, Hong Wang, Junlong School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan Province China

ISBN: (纸本)9784888983051

Since the passive safety system turns out to be a desirable method to achieve simplification and increase the reliability of the performance of essential safety functions, passive technology with inherent safety features has been generally applied to the design of advanced nuclear power plant. The PWR (pressurized water reactor) NPP (nuclear power plant) in this paper is a kind of mature pressurized water plants in China, and is proposed to be improved with some passive systems to enhance safety performance. The proposed and adapted passive safety systems for this PWR power plant in this paper contain: (1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);(5) the PRHRS (passive residual heat removal system), which is installed on the reactor coolant system (RCS) loop. In this research, the behaviors of passive safety systems are studied and transient characteristics of the primary and secondary side of the reactor during the Steam Generator Tube Rupture (SGTR) accident are investigated using the best-estimate transient simulation code Relap5/MOD3.3. Results reported in this paper indicate that making use of passive safety systems especially the PRHRS could ensure reactor safety during the SGTR accident. Copyright © 2018-2019 by JSME

关键词： Pressurized water reactors

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Numerical Comparison of Transpiration Cooling designs Using Real Gas Effects and Approximate Gas Model

Numerical Comparison of Transpiration Cooling Designs Using ...

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作者： Meng Wang Jianhua Wang Fei He Kang Qian Yadong Wu Guangsheng Zhu CAS Key Laboratory of Mechanical Behaviour and Design of Materials Department of Thermal Science and Energy EngineeringUniversity of Science and Technology of China Beijing Institute of Astronautical System Engineering

In the severe high-temperature environment caused by aerodynamic heating,the vibrational excitation,dissociation and ionization of gas may successively occur,which are known as real gas *** the real gas effects,the thermodynamic properties of gas vary drastically and significantly influence the performances of the active thermal protection system of hypersonic vehicles,especially in the case with coolant outflow,for example transpiration *** paper numerically investigates the transpiration cooling performance with the consideration of the interaction between coolant outflow and hypersonic flow under the real gas *** mathematical models and coupled numerical strategy are firstly validated by experimental data,then the influences of real gas effects on the transpiration cooling of a wedged leading edge(WLE) are studied under a flight Mach number range from 8 to 12 and a flight height of 40 *** analysis and discussions of the numerical results reveal some important phenomena and demonstrate the need to consider real gas effects.

关键词： Transpiration cooling real gas effects porous media hypersonic vehicles high-temperature environment

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Comparison of SGTR accident with two different passive residual heat removal systems 27

Comparison of SGTR accident with two different passive resid...

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Wu, Yirui Shan, Jianqiang Xu, Tao Ma, Haifu Yang, Junyun Yu, Hong Wang, Junlong Deng, Yaxin School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan Province China

ISBN: (纸本)9784888983051

Since the passive safety system turns out to be a desirable method to achieve simplification and increase the reliability of the performance of essential safety functions, passive technology has been generally applied to the design of advanced nuclear power plant. The traditional generation II+ nuclearpower plant is proposed to be improved with some passive systems to enhance safety performance. There are two series of passive safety systems for this kind of nuclear power plant in this paper, one of them contains: (1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);and (5) the PRHRS (passive residual heat removal system), which is installed on the reactor coolant system (RCS) loop;the other contains:(1) the RMT (reactor makeup tank);(2) the A-ACC (advanced accumulators);(3) the IRWST (in-containment refueling water storage tank);(4) the PDS (passive depressurization system);(5) the PEFS(passive emergency feed water system), which is installed on the secondary side of SGs. In this research, the transient characteristics of SGTR accident with the two different passive residual heat removal systems which are PRHRS and PEFS is investigated using the best-estimate transient simulation code Relap5/MOD3.3. The calculation results show that both of PRHRS and PEFS could remove the decay heat from the primary loop efficiently to ensure the reactor safety and reduce the radioactive leakage to mitigate the accident impact during the SGTR accident. Due to the significant cooling effect of PRHRS and PEFS, the water level of broken SG would not be overfilled in both conditions, which is different with the SGTR accident of traditionalgeneration II+nuclear power plant. Compared with the PEFS, the PRHRS performed better in cooling efficiency, long-term cooling performance, reducing radioactive leakage capacity and mitigating accident effect. Copyright © 2018-2

关键词： Nuclear power plants

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Analysis and verification of burnup algorithm in reactor 27

Analysis and verification of burnup algorithm in reactor

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Hu, Yuying Luo, Qi Yao, Dong Yu, Yingrui Liao, Hongkuan Zhou, Bingyan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9784888983051

Burnup algorithm analysis is an important part of the physical calculation in reactor. The computing accuracy of burnup algorithms is directly related to the correctness of the whole physical calculation. Due to the difference from the rates and lives of varieties of nuclides, burnup matrices are always sparse rigid exponential ones. At present, methods to solve exponential matrices are divided into two types, numerical methods and analytical methods. Besides, numerical methods conclude series methods, ordinary differential equation methods, polynomial methods, matrix decomposition methods and so on. In this study, some common methods to solve burnup matrices are introduced, such as Chebyshev Rational Approximation Method(CRAM), Krylov Subspace Method, Pade Approximation Method and Transmutation Trajectory Analysis(TTA). Analysis and verification for microscopic point-depletion calculation are carried out with two typical burnup chains. One of the burnup chains for verification is a decay chain of neptunium-237(237Np), which contains 13 nuclides. The other chain is an actinide nuclide reaction chain, including 25 nuclides from decay and neutron capture and 9 nuclides from fission. Because there is no close annual chain in the burnup chains used in verification, the results of using Transmutation Trajectory Analysis were thought to be accurate, and it has been used as the benchmark for comparative analysis of other methods. The final result shows, Chebyshev Rational Approximation Method has advantages in calculation accuracy and simplicity, and it is suitable to be used in large burnup calculations. Copyright © 2018-2019 by JSME

关键词： Isotopes

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Transverse Pelvic/Saddle Rotation Characterizing Push-Off Initiation During Saddle-Seat-Type Body-Weight-Supported Treadmill Walking

Transverse Pelvic/Saddle Rotation Characterizing Push-Off In...

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IEEE/RAS-EMBS International Conference on Biomedical Robotics and Biomechatronics (BioRob)

作者： Ryohei Terada Hiroaki Hirai Kosei Sasaki Hirokazu Kuga Keisuke Furukawa Kazuhiro Matsui Atsushi Nishikawa Hermano Igo Krebs Department of Mechanical Science and Bioengineering Graduate School of Engineering Science Osaka University Toyonaka Japan Department of Mechanical Engineering Massachusetts Institute of Technology Cambridge USA Department of Neurology University of Maryland School of Medicine Baltimore USA Department of Physical Medicine and Rehabilitation Fujita Health University Nagoya Japan Department of System Design Engineering Keio University Tokyo Japan The Wolfson School of Engineering Loughborough University Loughborough UK Programme Bioengineering Applied Science and Intelligent Systems University Campus Bio-Medico of Rome Rome Italy Healthcare Engineering Innovation Center (HEIC) Khalifa University of Science and Technology Abu Dhabi UAE Department of Mechanical Science and Bioengineering Osaka University Toyonaka Japan

ISBN: (数字)9798350386523

ISBN: (纸本)9798350386530

Background and Aim: A push-off event is a significant gait phase that contributes to initiating the swing leg and propelling the body forward. This study aims to explore a method for estimating push-off initiation, focusing on pelvic and saddle-seat motion peculiar to saddle-seat-type body-weight-supported (BWS) treadmill walking. Methods: The pelvic/saddle-seat rotation and ground reaction force during saddle-seat-type BWS treadmill walking were measured using an IMU sensor and a force plate in the treadmill, respectively. The hypothesis posits that the transverse rotational displacement of the pelvis and saddle seat aids in estimating push-off initiation. Results: The analysis results show that (1) the timing estimated from transverse pelvic rotation moderately agreed with push-off initiation timing (Spearman's rank correlation coefficient $\rho=0.59, \mathrm{p} < 0.01)$ , and (2) the timing estimated from transverse saddle rotation strongly agreed with push-off initiation timing $(\rho=0.67,\mathrm{p} < 0.01)$ . Conclusions: The utilization of a single IMU sensor requires a minimal setup for identifying push-off initiation, which contributes to reducing time, effort, and costs in clinical settings. This preliminary study using intact subjects should be a meaningful first step in the research for gait rehabilitation with saddle-seat-type BWS.

关键词： Legged locomotion Training Force measurement Force Focusing Propulsion Robot sensing systems Timing Pelvis Rotation measurement

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A Novel Torsion Instrument for Miniaturized Components Based on the Flexural Pivot

SSRN

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SSRN 2022年

作者： Liu, Dabiao Hu, Jianhui Liu, Hao Hu, Jiongjiong Luo, Tong Zhang, Zhiya Lei, Jian Hu, Peng Chen, Yanming He, Yuming School of Aerospace Engineering Huazhong University of Science and Technology Wuhan430074 China Hubei Key Laboratory of Engineering Structural Analysis and Safety Assessment Wuhan430074 China System Design Institute of Hubei Aerospace Technology Academy Wuhan430040 China Hubei Standardization and Quality Institution Wuhan430060 China

Torque measurement plays a significant role in characterizing microelectromechanical systems with rotation components and torsional behaviours of slender structures. A high-sensitivity torque transducer based on the flexural pivot with a wide measurement range is addressed. The torque transducer consists of a cylindrical flexural pivot acting as the elastic element, and an optical angle measurement system including dual laser displacement sensors. The instrument can measure the torque accurately using the flexural pivot with a known torsional spring constant. By selecting suitable pivots, it allows for a vast torque capacity ranging from 1.94×10 -4 to 1.91×10 -2 Nm, corresponding to a resolution ranging from 1.94×10 -9 to 1.91×10 -7 Nm. Torsion tests on Nylon 6 filaments, PET ribbons, and copper wires were performed with the instrument. The practicality and applicability of the method are confirmed. The developed instrument is a helpful tool for characterizing the mechanical properties of miniaturized components. © 2022, The Authors. All rights reserved.

关键词： Torsional stress

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