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Improvement of multi-functional properties by fabricating micro-pillar arrays structures on zirconium alloy surface

science China(Technological sciences) 2022年第6期65卷 1243-1252页

作者： WANG XiaoLiang WANG HaoYu LIU YongDa QI Min REN QuanYao XU Jie SHAN DeBin GUO Bin Key Laboratory of Micro-systems and Micro-structures Manufacturing of Ministry of Education Harbin Institute of TechnologyHarbin 150080China School of Materials Science and Engineering Harbin Institute of TechnologyHarbin 150001China Science and Technology on Reactor System Design Technology Laboratory Chengdu 610041China

Although using the microstructure of a surface to enhance specific functions has immense applicability in numerous fields,few studies have been conducted on the multi-functional properties of nuclear fuel elements in harsh *** this study,surfaces with zirconium alloy micro-pillar arrays were prepared using micro-milling and ultraviolet nanosecond laser technology,and their functional properties such as the wettability,structural stability,and corrosion resistance were *** was found that the geometric dimension of the micro-pillar arrays prepared using these two methods could meet the design requirements,but the micro-milling process had the best dimensional ***-nano multi-scale structures were obtained by laser ***,these multi-scale structures exhibited weak structural stability,and the nanostructures were easily *** contrast,the micro-pillar arrays manufactured using micro-milling were confirmed to have better structural stability and corrosion *** one hand,the area mass loss of the micro-milled structure was lower than that of a flat surface after experiencing high-pressure fluid scouring at 8 and 38 m/*** the other hand,the oxidation weight gain of the surface with the micro-milled structure was lower than that of a flat surface,and the oxide film was 22.5% thinner after 100 days of deionized water corrosion at 360℃ and 18.7 MPa.

关键词： zirconium alloy micro-pillar arrays wettability structural stability corrosion

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Anti-interference Study of Wireless Sensor Networks in Nuclear Power Plants 1

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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Deng, Zhi-guang Wu, Qian Lv, Xin Xiang, Mei-qiong Xu, Tao Qin, Yue Sun, Yong-sheng Peng, Ye-shun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (数字)9789819934553

ISBN: (纸本)9789819934546

The compatibility and anti-interference capability of wireless sensor networks within nuclear power plants in complex electromagnetic environments are the most essential elements to ensure reliable operation and effective combat of equipment within nuclear power plants in harsh environments. Interference signals generated by electrical, rotating and communication equipment and sensors attached to nuclear power plants, as well as malicious enemy interference sources, cause their electromagnetic environment to become increasingly complex. For the complex interference environment of nuclear power plant compartment, this paper firstly adopts supervised and unsupervised learning for interference cognition, and after obtaining the features of wireless interference sequences, anti-interference decision based on deep reinforcement learning and array antenna multi-domain anti-interference based on intelligent decision are implemented. From the intelligent interference simulation based on the physical transmission system, it can be seen that the proposed method can effectively identify and resist typical interference signals, which can bring reference to the anti-interference of nuclear power plants. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Research on Ultra High Flux Research reactor 23rd

Research on Ultra High Flux Research Reactor

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Zhang, Xue Yu, Hongxing Xia, Bangyang Li, Wenjie Zhang, Xilin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789819910229

The lack of fast neutron irradiation test equipment is a key practical factor that restricts the development of the new generation nuclear energy technology with fast reactor as the core in China. Scarce isotopes such as californium 242, which are urgently needed in industry and medicine, are also highly dependent on imports. In order to provide a fast reactor material irradiation environment and isotope production environment, significantly accelerate the development of fast reactor fuel and structural material technology, and improve the efficiency of rare isotope production, this paper proposes a multifunctional inherently safe ultra-high flux reactor design with fast/thermal neutron flux levels up to 1016 n/(cm2.s), namely UFR-1016. The neutron energy spectrum covers fast spectrum, superheat spectrum and thermal spectrum;several material irradiation test orifices, isotope production orifices and test loop orifices are arranged in the core, and the test loop supports many new reactor coolants such as H2O, Na, He, He-Xr, molten salt, etc., and supports the simulation of typical transient processes and accident conditions. This paper discusses the overall construction scheme of the reactor, and the current construction scheme shows that each performance index can meet the target requirements and achieve the expected functions while ensuring the safety performance of the reactor. This study can provide a basis for the development of ultra-high flux reactors and provide strong support for the cause of nuclear energy, nuclear technology, and nuclear medicine in China. © 2023, The Author(s).

关键词： Nuclear energy

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The Optimization design of the reactor Coolant system Based on Optimus 23rd

The Optimization Design of the Reactor Coolant System Based ...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Yanli, Yuan Xianhui, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811987793

Structural dynamic analysis of reactor coolant systems is an important means of evaluating the safety of nuclear power plants under seismic loads. The seismic load distribution of the equipment can be obtained through the dynamic analysis of the reactor coolant system, and the stress of the equipment can be analyzed. In order to reduce the seismic stress of the equipment, effectively reducing the seismic load of the equipment is an important way. In this paper, aiming at the problem of excessive load at the outlet nozzle of the reactor pressure vessel, combined with the design characteristics of the reactor coolant system under the seismic, the optimal design of the reactor coolant system is carried out by the OPTIMUS [1] which is a kind of software developed by Noesis Solutions Company, by which the multidisciplinary analysis processes can be integrated for collaborative optimization design, and ANSYS [2], MATLAB and other software can be integrated to automate the simulation processes. Firstly, a nonlinear model for the dynamic analysis of the reactor coolant system is established, and then the dynamic response sensitivity analysis of the reactor coolant system is carried out, from which the design variables for subsequent optimization analysis are selected, and then the optimization analysis is processed with the force load at the outlet nozzle of the reactor pressure vessel minimized as the target function, and with the force load at the inlet nozzle of the reactor pressure vessel, the bending moment load at the inlet nozzle of the reactor pressure vessel and the bending moment load at the outlet nozzle of the reactor pressure vessel as the state variables. The results show that after the optimization, the load at the outlet nozzle of the reactor pressure vessel is effectively reduced. Relevant optimization analysis methods and analysis processes can be extended to other systems and equipment in the nuclear power plants. © 2023, The Author(s), under exclusive li

关键词： Nozzles

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Effect of Corrosion Damage on Structural Failure Models Under Different Boundry Conditions 23rd

Effect of Corrosion Damage on Structural Failure Models Unde...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Qian, Sheng Sun, Yu Huangfu, Yuzhao Zhang, Ke Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811987793

Nuclear energy is an important means to deal with the energy crisis and global climate change, and the long-term safe operation of nuclear power plants strongly depends on the service behavior of structural materials. Nuclear power equipment is subject to complex multiple loads in actual situations, especially under compression, and even the buckling of tiny structures may have important safety hazards. Experience has shown that corrosion is an unavoidable result of nuclear power structures, and structures damaged by corrosion will cause internal stress redistribution under compression, resulting in changes in failure modes. This paper takes the most common uniform corrosion and pitting corrosion as the research objects, and explores the effects of different corrosion forms and corrosion parameters on the buckling failure of compression members under the same corrosion rate. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear fuels

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Research on Application of High Temperature and High Pressure Radar Liquid Level Measurement in Nuclear Power Plant 1

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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian Wang, Xue-Mei Xu, Si-Jie Zhu, Jia-Liang Dong, Chen-Long Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (数字)9789819934553

ISBN: (纸本)9789819934546

At present, the water levels of high-temperature and high-pressure vessels such as voltage stabilizers and steam generators on ships' nuclear power plants are measured by the pressure principle. Affected by the load conditions in the vessels, the differential pressure water level measurement has problems of low accuracy and low reliability. The radar type liquid level gauge has the advantages of high precision and high reliability, and is an effective means of measuring the liquid level of high temperature and high pressure containers. In this paper, a FMCW system split guided wave radar based on the principle of frequency domain reflection (FDR) is proposed for liquid level measurement. The antenna probe part and the electronics part adopt a split structure, and the electronics part is installed in the secondary instrument cabin with better environmental conditions., the radar is easy to meet the index requirements of shock, vibration and irradiation. The high-frequency signal emitted by the radar antenna is conducted along the coaxial rod probe, and the signal will be reflected only when it encounters the surface of the material, which effectively eliminates the influence of obstacles such as the heating plate in the container, the internal reference pipe water replenishment device and the reference pipe connection. Non-blind zone measurement of liquid level to meet the liquid level measurement requirements of high temperature and high pressure vessels in ship nuclear power plants. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Prospects for Next Generation Nuclear Power system 23rd

Prospects for Next Generation Nuclear Power System

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Zhang, Yaoxiang Yu, Hongxing Xia, Bangyang Li, Wenjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811988981

systematically research has been carried out on the demand of economic development for low-carbon clean energy and the opportunities faced by the development of nuclear power. A new generation of nuclear power technical index of "Inherent safety, Economics competitiveness, Environment-friendly, and Sustainability" has been formed, which provides guidance for the innovation and development of nuclear power technology. Considering the technical potential of various advanced reactor including the fourth-generation nuclear power system, inherently safe multi-purposed lead-cooled traveling wave reactor is proposed to solve the long-standing problems that have confronted nuclear power. The advanced reactor has attracted much attention because of their unique advantages in fuel supply issue, inherent safety, and economic efficiency. In this study, the main features of the advanced reactors are reviewed and current challenges in their development are pointed out. The advanced reactor obviates the fuel supply issues, including the nuclide enrichment, while making abundant natural uranium usable nuclear fuel. Each of these novel features is technologically separable, so that these new reactor design concepts can be also applied piecewise to enhance prospects in many different utilization circumstances. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear energy

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Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular reactor 23rd

Research on the Alarm Threshold for Steam Generator Tube Lea...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Xia, Ming-ming Wang, Jun-long Xu, Tao Huang, Bo-chen Zhu, Jian-ping Wu, Yi-rui Miao, Jian-xin Chen, Xin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sicuan Chengdu China

ISBN: (纸本)9789819910229

On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized water reactor nuclear power plants, the principle of setting for N-16 leak monitoring alarm thresholds of steam generator tube in small modular reactors is proposed, and the N-16 monitoring alarm thresholds are given. The calculation method for total gamma count rate of steam generator tube leak monitoring alarm thresholds of the small modular reactor is established, and the total gamma count rate under the condition of the leak corresponding to the N-16 monitoring alarm thresholds is calculated to guide the leak monitoring total gamma alarm thresholds set. © 2023, The Author(s).

关键词： Nuclear power plants

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Research and Application of Endogenous Security Active Defense technology for Domestic Nuclear Safety-Level Gateway Equipment 7th

Research and Application of Endogenous Security Active Defen...

引用

7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Li, Yong Liu, Ming-Xing Peng, Hao Hou, Rong-Bin Ma, Quan Wang, Ru-Qiao Liang, Gen-Hua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789819934546

Gateway is a protective equipment at the boundary of the nuclear safety-level I&C system. Aiming at the unknown threat across the boundary of information physical space, this paper studies several key technologies of active defense, and constructs the gateway deep secure architecture that can resist multilevel and multi-dimensional complex attacks. Firstly, the systematic control mechanism of the gateway is constructed, which mechanism includes access control for data flow, IP whitelist at network layer, function code whitelist at application layer, IP/MAC binding and the isolation mechanism of chip’s external ports. Secondly, based on the domestic trust root, the trusted chain from bootloader to the upper-layer application is built to guarantee the secure startup of the embedded system, and the key application processes are measured periodically and verified dynamically during the running process. Based on the above, from building equipment embedded trusted system environment to its security functions, a set of active security defense mechanisms of the gateway equipment sare formed, which enhances the security of the system and improves the information security protection n capability of the equipment. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Network security

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SMR FEEDWATER system ANALYSIS 30

SMR FEEDWATER SYSTEM ANALYSIS

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Zhu, Ye Liang, Qiao Xianwei, Liao Zhiyun, Cai Minghao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9784888982566

The once through steam generator has great heat transfer capacity and compact structure. Some small module reactors (SMR) applied once through steam generatorfor its high thermal efficiency. The thermal hydraulic characteristic of once through steam generator is different from traditional natural cycle steam generator as it doesn't contain water level. Thus the related feed water system is important for the steady operation of the power plant. Base on the thermal hydraulic characteristic of once through steam generator, SMR feed water system that contains process and control model is developed using APROS. The operating parameters are simulated under both different steady states and transient condition. The results show that both the thermal hydraulic and automatic control parameters of SMR feed water system can be simulated accurately in APROS. Reference and guidance can be provided for system optimization and safety analysis. © 2023 by JSME.

关键词： Water levels

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