检索结果-内蒙古大学图书馆

23rd IEEE International Conference on Software Quality, Reliability, and Security, QRS 2023

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

ISBN: (纸本)9798350319583

Modified Condition/Decision Coverage (MC/DC) is a test coverage standard with excellent fault detection capability, which is widely used in testing safety-critical software. Symbolic execution generates test cases automatically to achieve high code coverage. However, since symbolic execution uses short-circuit evaluation to evaluate decisions, it fails to guarantee the consistency of other conditions in a decision required by the MC/DC criterion. As a result, it is incapable of generating MC/DC test cases to test safety-critical systems adequately. To solve this problem, we propose Branch Dependence Guided Symbolic Execution (BDGSE), a symbolic execution technique for high MC/DC. The approach utilizes static analysis to compute the branch dependencies, then guides symbolic execution to selectively explore paths and simplify test cases, and finally generates a small number of test cases to achieve high MC/DC coverage. Our experimental results show that BDGSE can generate high-quality test cases. Although BDGSE generates fewer test cases, it can achieve higher MC/DC coverage than SPF and random methods, and the fault detection capability of test cases generated by BDGSE is comparable to that of test cases generated by SPF. © 2023 IEEE.

关键词： Software testing

来源：评论

学校读者我要写书评

暂无评论

Research of SSAE-GPC in Coordinated Control System of Nuclear Power Plant 5th

Research of SSAE-GPC in Coordinated Control System of Nuclea...

引用

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

作者： Deng, Zhi-Guang Wu, Qian Zhu, Bi-Wei Lv, Xin Zhu, Jia-Liang Xu, Si-Jie Wang, Xue-Mei National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610213 China

ISBN: (纸本)9789811634550

For the problem of poor control effect of conventional PID controllers in complex systems, this paper fully combines the advantages of deep learning in feature extraction, regression prediction, and predictive control in dealing with multivariable, strong coupling and other issues. Firstly, the predictive model controller is constructed through the stacked sparse auto-encoder (SSAE) deep network, and then the stepped generalized predictive control (SGPC) is used as the rolling optimization controller. Thus, the SSAE-SGPC neural network predictive controller is built. Finally, a simulation experiment is carried out in the dual-input dual-output multi-variable coordinated control system of nuclear power plant. Through a series of simulations such as set value disturbance, internal disturbance and external disturbance, compared with conventional PID control, SSAE-GPC controller has better control effect. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Controllers

来源：评论

学校读者我要写书评

暂无评论

Cybersecurity Risk Assessment of Nuclear Svdu Based on Attack Tree

SSRN

引用

SSRN 2025年

作者： Wu, Yanqun Wang, Junfeng Ma, Quan Liu, Mingxing Chen, Meiyuan College of Computer Science Sichuan University Chengdu610065 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610000 China

The nuclear power SVDU in nuclear power plants is an important component of the nuclear reactor protection system. With the complete digitalization of the reactor protection system, the risks of cybersecurity attacks have significantly increased. This paper proposes a safety risk assessment method based on an attack tree model to analyze the risk status of the nuclear power SVDU and assess its risk level and security level. Firstly, the typical information security threats faced by nuclear power SVDU are analyzed. Subsequently, an attack tree model of the system is constructed based on the STRIDE model, with four security attributes assigned to the leaf nodes of the tree with reference to the CVSS4.0 system and multi-attribute utility theory. These attributes are quantified through level scoring, and the risk probability of the leaf nodes is calculated using entropy weighting. The risk probability of the root node is then obtained based on the dependency relationship between nodes. Finally, the security risk rating of nuclear power SVDU is obtained. Experimental results demonstrate that the method in this paper more accurately identifies high-risk security threats, predicts possible attack paths, and provides a basis for security protection strategy selection. © 2025, The Authors. All rights reserved.

关键词： reactor shielding

来源：评论

学校读者我要写书评

暂无评论

Application of feedforward predictive control in DC furnace coordination system

Application of feedforward predictive control in DC furnace ...

引用

2020 International Symposium on Automation, Mechanical and design Engineering, SAMDE 2020

作者： Deng, Zhiguang Zhengxi, H.E. Biwei, Z.H.U. Jialiang, Z.H.U. Xin, L.V. Qian, W.U. National Key Labortory of Science and Technology on Reactor System Design Technology Chengdu610213 China

In order to solve the control difficulties such as large dynamic delay, serious coupling between machine and furnace and strong nonlinear, the feedforward and feedback predictive control is proposed to control the coordinated system on the basis of multi-model predictive control, and the static feedforward part designs the feed line feedforward of coal quantity against coal quality disturbance on the basis of the accurate balance of energy. Thus, the reference total fuel quantity under the target load instruction is determined, and the dynamic part fully considers the dynamic compensation of the unit energy storage, gives a certain overshoot fuel quantity to the boiler regulation, speeds up its response, and ensures the rapidity of the unit. The real-time simulation results of virtual DPU (Distributed Processing Unit) show that the designed feedforward-feedback predictive control can quickly respond to load change, improve the resistance to fuel disturbance, reduce the fluctuation of main steam pressure, and better ensure the safe, economic and stable operation of the coordination system. © Published under licence by IOP Publishing Ltd.

关键词： Feedback

来源：评论

学校读者我要写书评

暂无评论

Structures and energetics of semicoherent interfaces of precipitates in hcp/bcc systems:A molecular dynamics study

引用

Journal of Materials science & technology 2021年第8期67卷 50-60页

作者： Jin-Yu Zhang Fu-Zhi Dai Zhi-Peng Sun Wen-Zheng Zhang Key Laboratory of Advanced Materials(MOE) School of Materials Science and EngineeringTsinghua UniversityBeijing 100084China Science and Technology of Advanced Functional Composite Laboratory Aerospace Research Institute of Materials&Processing TechnologyBeijing 100076China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610041China

α/β(hcp/bcc)interfaces are of great importance in the microstructure development and the mechanical properties of titanium and zirconium *** work contributes to the study of interface energetics and interfacial structures of the precipitate in the hcp/bcc system based on a simulation study using molecular statics(MS)and molecular dynamics(MD).The input orientation relationship(OR)was calculated based on the O-line *** on the energy of the interfaces containing the invariant line(IL),two preferred facets were determined by the Wulff construction,which explained the observed orientations of the habit plane(HP)and the side facet(SF).The deviation of the observed precipitate morphology from the equilibrium shape was discussed in terms of interface *** structures of the interfaces surrounding a three-dimensional(3 D)precipitate,including the preferred facets and the end face,were obtained at the atomic *** simulated dislocation structures and atomic structures in these interfaces are in good agreement with those of the experimental observations for Ti-Cr alloys.A method was suggested for modifying the O-cell structure with the guidance of the relaxed structure,yielding consistency between the calculated dislocation structure based on the generalized O-element approach and the simulation results.

关键词： Interface Misfit dislocation Precipitate

来源：评论

学校读者我要写书评

暂无评论

Research of Advanced Control Algorithm in Primary Loop Control System 5th

Research of Advanced Control Algorithm in Primary Loop Contr...

引用

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

作者： Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian He, Peng Xiang, Mei-Qiong Xu, Tao Qing, Yue National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610213 China

ISBN: (纸本)9789811634550

The primary loop system of nuclear power plant is a large-scale control system with serious coupling between loops and complex objects. In order to solve the problem of integrated control of primary loop core power, stabilizer pressure and water level, and steam generator water level, this paper applies improved predictive control algorithms to each sub-control system on the basis of mechanism modeling. For the strong non-linear problem of water level control, a multi-model predictive controller is constructed through linearization at each typical operating point. The simulation results show that the application of advanced predictive control algorithm to the primary loop control system has achieved good control performance, and it also lays a solid foundation for subsequent practical engineering applications. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Water levels

来源：评论

学校读者我要写书评

暂无评论

Assessment of Coupled Effect of Steam Pipes on Seismic Analysis of reactor Coolant System 7

Assessment of Coupled Effect of Steam Pipes on Seismic Analy...

引用

7th International Conference on Environmental science and Civil Engineering, ESCE 2021

作者： Li, Lijuan Liu, Zhenyu Li, Hui Ye, Xianhui Ai, Honglei National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu Sichuan China

reactor coolant system is connected with auxiliary pipes, surge pipes and steam pipes. In order to facilitate the dynamic analysis of reactor coolant system, it is necessary to decouple the pipes connected with the reactor coolant system. Although some international standards stipulating requirements for the decoupling of subsystems from the main system, in order to further explore the influence of decoupling steam pipes, the seismic response of reactor coolant system with or without steam pipes is simulated by using ANSYS program. Firstly, the modal analysis of reactor coolant system is carried out to analysis the influence of steam pipes on the resonant frequency of reactor system. Then, the standardized seismic dynamic analysis of reactor system with or without steam pipes is carried out. The nozzle load (inlet and outlet nozzle load of main device, such as reactor pressure vessel, steam generator, pump) and support load (of main device such as reactor pressure vessel, steam generator, pump) are output and compared. According to nozzle load and support load, it can be seen that the steam pipes have little influence on the seismic analysis of reactor coolant system, i.e. steam pipes can be decoupled in the seismic analysis of reactor coolant system. © Published under licence by IOP Publishing Ltd.

关键词： Steam generators

来源：评论

学校读者我要写书评

暂无评论

The Influence of Turbulators on the Flow and Heat Transfer Characteristic of Helium-Xenon Mixture Inside the Tight Lattice Rod Bundles

SSRN

引用

SSRN 2024年

作者： Wang, Lanxin Shi, Xinhuan Li, Zhongchun Wu, Xiaoli Ding, Shuhua Chen, Wei School of Aeronautics and Astronautics Sichuan University Chengdu610065 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China

The gas-cooled nuclear reactor combined with the closed Brayton cycle is the ideal choice for future high-power space missions, while the helium-xenon mixture is a suitable working medium for the reactor due to its good compressibility and heat transfer capacity. For further development and application of more lightweight compact reactor, the influence mechanism of turbulator structures with different angle and layout on the heat transfer enhancement of helium-xenon mixture in the sub-channel of gas-cooled nuclear reactor is numerically studied. The results show that, due to the vortex and secondary flow induced by the turbulator, the heat transfer is enhanced effectively, and the Nusselt number is fluctuated periodically. Compare the result with different angle, the heat transfer enhancement by the turbulator with 90°angle is relatively small, and the pressure drop is large. Because of the secondary flow in narrow triangular space induced by turbulator with 45°angle, the mixing between the high and low temperature fluids will effective enhanced, the heat transfer enhancement is more significant. The heat transfer performance and thermal efficiency index of different turbulator layout are summarized and compared, which provides the reference for heat transfer design of gas-cooled nuclear reactor. © 2024, The Authors. All rights reserved.

关键词： Helium

来源：评论

学校读者我要写书评

暂无评论

EXPERIMENTAL STUDY ON HEAT TRANSFER CHARACTERISTICS OF HIGH TEMPERATURE HEAT PIPE WITH CAPILLARY WICK DURING EVAPORATION 30

EXPERIMENTAL STUDY ON HEAT TRANSFER CHARACTERISTICS OF HIGH ...

引用

30th International Conference on Nuclear Engineering, ICONE 2023

作者： Zhou, Zheng Ma, Yugao Wu, Qi Ma, Zaiyong Sun, Wan Zhang, Luteng Zhu, Longxiang Pan, Liangming Key Laboratory of Low-grade Energy Utilization Technologies and Systems Ministry of Education Chongqing University Chongqing400044 China Department of Nuclear Engineering and Technology Chongqing University Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9784888982566

Due to the surface covered by the capillary wick in the high temperature heat pipe, the classical evaporation and condensation model may be difficult to characterize the evaporation process well in the high temperature heat pipe under different working conditions. Therefore, this paper carried out an experimental study on the heat transfer characteristics of the evaporation process of high temperature heat pipe with capillary wick. By measuring the axial and radial temperature distribution in the high temperature heat pipe under different working conditions, the phase interface evaporation thermal resistance and evaporation coefficient (Hertz-Knudsen equation) at different temperatures in the high temperature heat pipe were calculated, and the variation law of evaporation coefficient under different working conditions was analyzed. The results show that the magnitude of the evaporation thermal resistance is between 0 and 10-3, which means the evaporation heat transfer coefficient is very high. In general, with the increase of temperature(pressure), the logarithm of evaporation coefficient has a good negative linear correlation with pressure. In addition, it is found that if the adiabatic section temperature commonly used in engineering calculation is taken as the saturation temperature, the value of evaporation coefficient obtained is relatively small, as well as the data dispersion, which is due to axial thermal resistance is introduced. Furthermore, by fitting the experimental data, a correlation for the evaporation of high temperature heat pipe with capillary wick is proposed. © 2023 by JSME.

关键词： Evaporation

来源：评论

学校读者我要写书评

暂无评论

An Interpretable Dynamic Feature Search Methodology for Accelerating Computational Process of Control Rod Descent in Nuclear reactors

SSRN

引用

SSRN 2023年

作者： Huang, Qingyu Xiao, Cong Pang, Zhixin Lin, Yuanfeng Liu, Jia Zhang, Zhuo Zhao, Mengwei Liu, Xiaobo Wang, Yuanmei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Within the operational dynamics of a nuclear reactor, the customary approach involves modulating the reactor's power output by means of control rod manipulation, which effectively alters the neutron density across the core. The descent behavior of the control rod drive lines pertains to the intricate motion exhibited by the control rod components within the reactor during its operational lifespan, characterized by conditions of heightened irradiation, temperature, pressure, and complex fluid dynamics. The precise calculation of the control rod descent process is an integral facet of reactor structural design to ensure the safe and reliable operation of the reactor. However, the current computational fluid dynamics-based simulation methods employed for this purpose necessitate extensive grid computations, imposing significant computational burdens in terms of resources and time. In light of this challenge, we present a novel and interpretative algorithm rooted in dynamic similarity feature search. Through comprehensive validation, this algorithm demonstrates remarkable precision with computational results exhibiting an error margin within 10%, while simultaneously achieving a substantial enhancement in computational efficiency of nearly three orders of magnitude when compared to conventional computational fluid dynamics techniques. Notably, this algorithm showcases exceptional versatility, holding immense promise for broad applicability across various operational scenarios encountered during the intricate process of nuclear reactor design. © 2023, The Authors. All rights reserved.

关键词： Control rods

来源：评论

学校读者我要写书评

暂无评论

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案：

请选择收藏分类：

通借通还

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：