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检索条件"机构=Reactor System Design Technology Laboratory"

共 651 条记录，以下是91-100 订阅

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Study on 131I Source Term in reactor Coolant Under Shutdown Transient Condition 23rd

Study on 131I Source Term in Reactor Coolant Under Shutdown ...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Fu-ting, Jing Huan-wen, L.V. Ming-Ming, X.I.A. Zhang-Han, Y.E. Xi-long, Gao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Fuqing Nuclear Power Co. Ltd Fuqing China

ISBN: (纸本)9789811988981

131I activity in coolant under transient conditions is an important input for SGTR accident source term analysis in nuclear power plant, which directly affects whether the radioactive consequences of SGTR can meet the regulatory requirements. Based on the measurement results of 131I source term of several units in nuclear power plant A during shutdown, this paper study the variation law of 131I source term in the transient process of shutdown, analyzes the causes of 131I peak release, calculates the 131I release rate in the transient process, and obtains the following conclusions: 1) the 131I release rate based on the measured value is significantly lower than that used in the current safety analysis;2) The larger the fuel rod break size, the smaller the peak factor of 131I in the primary circuit during transient. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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design of Code Generator for Safety Level I&C Software of NPPs 6th

Design of Code Generator for Safety Level I&C Software of NP...

引用

6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Wei, Jiang Lin, Lan Bin, Yang Hou, Rong-Bin Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of the China Sichuan Chengdu China

ISBN: (纸本)9789811911804

The function block diagram is used to design control algorithm of nuclear safety-level I&C (Instrumentation & Control) system. Then it is converted into C code by code generator. And the C code is downloaded into embedded software platform of NASPIC after compiled by a common C compiler. Therefore, the credibility of the code generator is directly related to the safety of nuclear power plant operation. At present, the methods which are used to guarantee the credibility of code generators mainly include test and V&V. However, the formal method describes the software system from a mathematical point of view and verifies its correctness of translation processes, which can improve the credibility of the code generator to the greatest extent. Based on the formal method and compilation technology, this paper introduces the design and implement of code generator for safety I&C software. A initial test has been performed to check the requirement of nuclear I&C software development. The test results show that the code generator can translate Lustre program into C program. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Constructing Basic Probability Assignment Based on the Slope Correlation Degree 5

Constructing Basic Probability Assignment Based on the Slope...

引用

5th IEEE International Conference on Electronics technology, ICET 2022

作者： Chen, Jie Yang, Pengcheng Pu, Xiaofei Xie, Hao Wang, Jinxin Wu, Kunren Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China

ISBN: (纸本)9781665485081

DS evidence theory can be applied to deal with multi-sensor data and get reliable and accurate decision result of system's target or object due to its good measurement and reasonable description of system's uncertainty. In practical application field, DS evidence theory is achieved by two steps, one is the acquisition of the basic probability assignment function (BPA), and the other is the synthesis of multiple evidences that is obtained from multi-sensor data. The existing relevant literatures mainly solve the combination problem of conflict evidences, while lack of systematic research on the acquisition of BPA. In this paper, we focus on the discussion and innovation of the acquisition of BPA. BPA in DS evidence theory is the basic unit to describe the uncertainty of the system and evidences, which fundamentally determines its superiority with respect to probability theory and Bayesian reasoning. Getting a reasonable and effective BPA is the premise of the application of DS evidence theory. Traditional BPA acquisition methods have the limitations like absent priori knowledge and low acquisition accuracy. Aiming to solve the technical difficulties of traditional methods, we put forward a new BPA acquisition algorithm based on the slope correlative degree. The novel algorithm proposed in this paper successfully realizes the reliable descriptions of system's uncertainty, which is conducive to product the accurate BPAs and the precise fusion results. Experimental results and analyses demonstrate that the innovative algorithm can not only produce reasonable BPAs, which can better fit the sensors' monitoring data, but also expand the gap between the support degree of different propositions in BPA, which is more beneficial to the synthesis of evidences and the decision fusion of the system. Thus, the novel BPA acquisition algorithm has great application value and research significance. © 2022 IEEE.

关键词： Uncertainty analysis

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RESEARCH ON LOCA DYNAMIC ANALYSIS MODEL OF reactor system 29

RESEARCH ON LOCA DYNAMIC ANALYSIS MODEL OF REACTOR SYSTEM

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Liu, Shuai Harbin Engineering University Harbin China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9780791886472

The reactor system has a large scale of components. And the system dynamic analysis model for loss of coolant accidents(LOCA) contains many non-linear factors. The transient calculation analysis takes a long time and the convergence is difficult to guarantee. In this paper, two different analysis models (complete three-loop model and single-loop model) of the reactor loop system are established for comparative analysis. The analysis shows that the calculation error of the main position load in the two different model is within 10%. The decoupling influence of the surge tube and the reactor inlet and outlet on the system dynamic characteristics is within an acceptable range. When the single-loop model is used, it is necessary to decouple the reactor pressure vessel and pressurizer. And the simplified boundary is adapted to simulate its effect on the whole loop. The single-loop dynamic analysis model based on the decoupling criterion can greatly reduce the calculation scale and meet the calculation accuracy, which can be used to calculate the LOCA dynamic characteristics of the reactor system quickly. The model can also be used for seismic analysis of reactor system. And using this model for reactor system dynamic analysis can greatly improve the calculation efficiency. Copyright © 2022 by ASME.

关键词： Loss of coolant accidents

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Application Verification of Wireless Sensor Network in Nuclear Power Plant 1

引用

6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Deng, Zhi-Guang Wu, Qian Xiang, Mei-Qiong Dong, Chen-Long Qin, Yue Li, Zhuo-Yue Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (数字)9789811911811

ISBN: (纸本)9789811911804

The application of wireless sensor network in nuclear power plant can greatly reduce the workload of nuclear power plant cable wiring, and help to improve the automation and information level of nuclear power plant. However, its application also faces the constraints of strong electromagnetic interference, high temperature and other special complex nuclear environment, especially the narrow multi metal enclosed space of nuclear power plant cabin, which brings challenges to the application of wireless sensor. Based on the Lora wireless protocol, this paper studies the low-power selection of wireless sensor and MCU, sleep / wake-up low-power mechanism, dual star adaptive frequency hopping anti-interference, frequency division and time division multi node real-time communication and other aspects. On this basis, the prototype is developed, and the functional test, high and low temperature test, electromagnetic compatibility test and bench test are carried out. The feasibility of wireless sensor application in nuclear power plant is preliminarily verified, which lays a foundation for further application. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Wireless sensor networks

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Direct Contact Condensation Characteristics of Steam Injection into Cold-Water Pipe Under Rolling Condition 23rd

Direct Contact Condensation Characteristics of Steam Injecti...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789819910229

Direct contact condensation (DCC) is widely occurred in nuclear power systems and leads to undesired phenomena such as condensation-induced water hammer. For ocean nuclear power ships, DCC is inevitable in the passive heat removal system and influenced by sea conditions. In this paper, the characteristics of DCC under rolling conditions are analyzed. The numerical model of DCC is established based on computational fluid dynamics approach. The VOF model, SST k–ω turbulence model and the additional inertia force model are incorporated to describe the liquid-gas two-phase flow under the rolling motion. The condensation model based on surface renewal theory (SRT) is used to simulate steam-water DCC phenomenon. The simulation results are compared with the experimental data and show reasonable agreement. The effects of rolling motion on DCC for steam injection into a horizontal pipe filled with cold water are numerically investigated. The results show that the additional inertial forces and the average condensation rate increase with the increase of the rolling angle and frequency. The reverse flow of the seawater induced by rolling motion leads to the accumulation of the steam at the lower part of the pipe, resulting in a large pressure pulse. With the increase of rolling angle and frequency, the pressure pulse induced by DCC increases. © 2023, The Author(s).

关键词： Condensation

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Research on Switch Signal Transmission system Based on Optical Fiber 1

引用

6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Xiang, Mei-Qiong Zhu, Jia-Liang He, Zheng-Xi Deng, Zhi-Guang Dong, Chen-Long Li, Zhuo-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)9789811911811

ISBN: (纸本)9789811911804

Nuclear power plants need to transmit a large number of switch signals, while traditional electrical transmission of switch signals requires a large number of cables, which makes it difficult to realize self-inspection of transmission path faults and is vulnerable to electromagnetic interference. In view of the needs of a large number of switch signal transmission and the shortcomings of traditional electrical methods, this paper developed two sets of switch signal transmission systems based on optical fiber, which realized the simultaneous transmission of 16 channels and 2 channels of switch signals on one optical fiber, and had the function of transmission path fault self-checking. It has the advantages of wide frequency response range, small transmission delay, high reliability and strong environmental tolerance, and has broad application prospects. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Optical fibers

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CFD ANALYSIS ON THE SMALL MODULE reactor (ACP100) PRS RETURN LINE THERMAL STRATIFICATION PHENOMENON 29

CFD ANALYSIS ON THE SMALL MODULE REACTOR (ACP100) PRS RETURN...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Peiying, Li Cai, Zhiyun Zhang, Yulong Liu, Hang Liu, Minghao Ye, Zhu Tao, Shuchang Liu, Xianghong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9780791886434

The return line of the passive residual system(PRS) of ACP100 is connected to the direct injection nozzle of the pressure vessel. It is a non-isolated dead pipe containing coolant, and there is no insulation layer. The temperature difference between the two sides of the pipe is large, which is prone to thermal stratification. This paper uses FloEFD software to carry out CFD simulation analysis and research on the thermal stratification phenomenon of the pipeline in normal operation and accident conditions. The scope of the return line analysis in this paper begins with the isolation valve at the outlet and ends with the direct injection nozzle on the pressure vessel. The finite volume method is used to solve the model, and the standard k-Ε two-equation model is used for turbulence simulation. The pipeline system adopts a mesh refinement strategy according to the flow channel and wall thickness in the pipeline to obtain a reasonable mesh distribution. The results show that during normal operation, there is obvious thermal stratification at the exit of the PRS isolation valves, and there is a certain vortex in the tube, which can promote the heat exchange between the reactor pressure vessel and the PRS return pipeline;When PRS put into operation, a large temperature gradient is generated at the interface of the annular cavity of the pressure vessel, and the influence of thermal stress and cyclic thermal shock needs to be considered, and an obvious vortex will be formed nearby to promote the rapid heat exchange of cold and hot water in the nearby area. The result of this paper can provide input for PRS return line thermal stress and thermal cycling impact analysis. Copyright © 2022 by ASME and a non-US government agency.

关键词： Vortex flow

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The Application of Different Distance Functions in DS Evidence Theory 5

The Application of Different Distance Functions in DS Eviden...

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5th IEEE International Conference on Electronics technology, ICET 2022

作者： Chen, Jie Li, Yiliang Zhao, Mengwei Huang, Ke Wu, Kunren Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China

ISBN: (纸本)9781665485081

DS evidence theory is a widely used uncertainty inference algorithm for decision fusion that can fuse this complementary and redundant information to reduce the uncertainty of the system. Evidence conflict is the most common problem in the application of DS evidence theory, and how to resolve the conflict is the key to obtaining reasonable and reliable decision results. To resolve the evidence conflicts, numerous scholars have used different distance functions to improve the DS combination rule to effectively manage the conflicting evidence. However, there are only few relevant studies that address the performance of different distance functions for handling evidence conflicts. Therefore, this paper discusses the performance of five distance functions (Euclidean distance function, Manhattan distance function, Minkowsky distance function, Jffreys distance function and Camberra distance function) to handle evidence conflicts by performing simulations in a fault diagnosis system for typical mechanical vibration signals. © 2022 IEEE.

关键词： Failure analysis

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Effects of Inlet Conditions on the Two-Phase Flow Water Hammer Transients in Elastic Tube 23rd

Effects of Inlet Conditions on the Two-Phase Flow Water Hamm...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Zhao, Zixiang Duan, Zhongdi Xue, Hongxiang Yuan, Yuchao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789819910229

Two-phase flow water hammer events occur in the pipelines of the nuclear power systems and lead to transient and violent pressure shock to tube structures. For the sake of operation safety, the occurrence and severity of the two-phase water hammer should be carefully assessed. This paper presents a parameter analysis of the inlet conditions on the two-phase flow water hammer transients, with considering the elastic effect of the tube walls. A numerical model is established for the vapor-liquid two-phase flow based on the two-fluid six-equation modelling approach, with incorporating correlations and criterions for two-phase flow regime, interfacial interactions and heat transfer. The governing equations are transformed to matrix form expressed by characteristic variables, and solved using the splitting operator method and the total variation diminishing scheme. The accuracy of the model is verified against the experimental data in open literature. Then, the model is applied to investigate the effect of inlet velocity and inlet water temperature on the two-phase flow water hammer transients. The simulation results show that the increase of inlet velocity increases the pressure peak values and brings forward the onset of water hammer, and the increase of inlet temperature decreases the pressure shock. A comparison of the water hammer results between the elastic tube and rigid tube is further presented, and the effect of the elastic modulus on the water hammer is analyzed. The results also show that the pressure peak is largely affected by the tube diameter. © 2023, The Author(s).

关键词： Condensation

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