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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Wang, Xiaotong Luo, Ying Dong, Yuanyuan Yao, Weihua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791883785

Irradiation hardening is one of the most important aging effects of reactor pressure vessel (RPV) steel in long-term service. A number of studies have indicated that irradiation hardening is mainly caused by irradiation induced defects, such as dislocation loops and precipitates. In this paper, we have simulated the irradiation damage of low-copper reactor pressure vessel (RPV) steel. The generation of Mn-Ni-Si precipitates is simulated by the cluster dynamics model based on rate theory. On this basis, the crystal plasticity finite element method based on modified crystal plasticity model is used to simulate the effect of Mn-Ni-Si precipitates on the mechanical properties of RPV steels. The simulated results has been compared with the experimental results from the literature. By coupling the cluster dynamics and the crystal plastic finite element method, we suggest a multi-scale simulation method to simulate and predict irradiation damage of RPV steel. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Finite element method

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Burnup performance analysis for candidate materials of the LWR accident tolerant control rod 14

Burnup performance analysis for candidate materials of the L...

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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019

作者： Liu, Yong Li, Mancang Yu, Yingrui Xiao, Peng Wang, Xingbo Zhang, Bin Wang, Dongyong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# Section 1 Changshun Avenue Chengdu China

The accident tolerant fuel (ATF) is considered to be one of the most advanced concepts to improve the safety of light water reactors (LWRs). The accident tolerant control rod (ATCR) is a significant aspect in the ATF concept. The melting temperature of traditional LWR control rod (CR) materials, such as silver-indium-cadmium (AIC) alloy, is too low to endure the high temperature under several accident conditions. Consequently, varieties of candidate materials for control rod have been proposed in the previous researches because of the outstanding characters of high-temperature behavior, as well as reactivity worth, stability in coolant water and so on. In this paper, the burnup performance of the sesquioxides of the rare-earth elements (RE2O3) and the hafnia (Hf) are analyzed and compared to the traditional AIC control rod. Two parameters are chosen to reveal the burnup performance of the candidate control rod materials, the initial control rod reactivity worth and the stability of the control rod reactivity worth along with the assembly burnup. The candidate-material control rods and the AIC control rod are placed in the ATF assembly with the same conditions, and the assembly is depleted to sufficient burnup. Numerical results indicate that Eu2O3, Dy2O3, Sm2O3 and Hf are excellent ATCR materials compared to AIC. The initial control rod reactivity worth of these materials is not less than that of AIC, and the burnup stability is outstanding, especially Eu2O3 and Dy2O3 Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water reactor Fuel Performance *** rights reserved.

关键词： Hafnium oxides

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Formally Verified a Front-End of the Trusted Code Generator for Safety I&C Software of NPPs 5th

Formally Verified a Front-End of the Trusted Code Generator ...

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

作者： Lan, Lin Ma, Quan Hou, Rong-Bin Jiang, Wei Liu, Ming-Xing Yang, Fei Li, Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China Harbin Engineering University Harbin China

ISBN: (纸本)9789811634550

In nuclear power plant embedded software control area, graphical control algorithms are described by Lustre program and designed with graphical editors of engineering station. After they are translated into C programs through a code generator, then the C programs are downloaded to the embedded platform software of NASPIC. The correctness of the code generator will directly determine the credibility and safety of NASPIC. Therefore, it’s important to ensure the correctness of the code generator translation process. Formally verified the correctness of a code generator, which has been studied for many years and becomes a most effective approach to develop a trusted code generator. This article is based on the requirements of nuclear safety-level I&C (Instrumentation & Control) system and mainly presents the development of a formally verified code generator front-end. The front-end translates Lustre source program into S_Lustre (a sequential intermediate language). And it is programmed and proved in Coq (Auxiliary Theorem Prover). During the development of the front-end, two key technical challenges have been resolved. The first is to ensure every id which appeared in the Lustre program has been defined. The second is to implement the casualty analysis and determine the evaluation order of user-defined types and equations based on the dependencies. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Formal verification

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DC-Side Decoupling Method of DC-link Capacitor Reduction for Single Phase PWM Rectifier

DC-Side Decoupling Method of DC-link Capacitor Reduction for...

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2020 IEEE Sustainable Power and Energy Conference, iSPEC 2020

作者： Wang, Jinxin Renyong, Peng Dai, Kailei Zhang, Zhiqiang Zhang, Ting Zhao, Junjie Chen, Qian Zhang, Jianjian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9781728191645

The integrated charging system of Electric vehicle consists of a single-phase PWM rectifier and a Buck converter. When the single-phase PWM rectifier works with unit power factor, the dc-link voltage contains a large voltage harmonic of twice the grid frequency. Although the output voltage ripple can be controlled within the required range using the proper control of the Buck converter, the second-order harmonic on the dc-link capacitor is inevitable. This paper proposes a de-side decoupling method for the second-order harmonic problem of the dc-link voltage of the integrated charging system. A de-side decoupling half bridge is connected in parallel to absorb the ripple power of twice the grid frequency. This paper analyzes the operating principle of the de-side decoupling half bridge. Based on a theoretical analysis of the topology and the design procedure for controlling system, the proposed converter is designed and simulated. Finally, simulation results are given to verify the method. © 2020 IEEE.

关键词： Pulse width modulation

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Study on the thermal-mechanical performance of SiC composites cladding under multiple conditions

Study on the thermal-mechanical performance of SiC composite...

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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Yin, Chunyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.328 section 1 changshun avenue Chengdu China

ISBN: (纸本)9780791883761

SiC has become a candidate cladding material of Accident Tolerant Fuels (ATF) due to its excellent irradiation stability and corrosion resistance. However, because SiC is a ceramic material with low toughness, brittle failure is a significant concern. In order to improve the toughness, SiC fiber is required to manufacture multi-layer SiC composites. But the current performance model or analysis tool is not available for SiC composites cladding due to its obviously difference with Zr alloy cladding. On one side, Finite element method was used in this paper to analyze the performance of SiC composites cladding under operation conditions which include normal, transient conditions and LOCA conditions;on the other side, this paper gives the performance of the SiC composites with two layers under multiple operating conditions. The result showed that the temperature was stable and the maximum hoop stress was reached at about 70d under normal condition. The power ramp can increase the cladding temperature and has visible influence on the stress distribution. The hoop stress of the cladding reversed under LOCA condition. The tensile hoop stress on the outer surface significantly increased, which caused the obvious increase of failure probability of monolithic SiC, and the failure probability of SiC layer is significantly increased. The conclusion of the analysis has guiding significance for the theoretical design of SiC composites. Copyright © 2020 ASME.

关键词： Silicon carbide

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Research on Output Torque Optimization of Ultrasonic Motor Based on Genetic Algorithm 17th

Research on Output Torque Optimization of Ultrasonic Motor B...

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17th Annual Conference of China Electrotechnical Society, CES 2022

作者： Li, Xiaoyang Tang, Jiankai Yang, Bo Wu, Hao Xu, Qiwei Yang, Yun The State Key Laboratory of Power Transmission Equipment & System Security and New Technology Chongqing University Chongqing400030 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

ISBN: (纸本)9789819904501

Aiming at the problem of small output torque in the design process of traveling to wave ultrasonic motor, this paper proposes a method of optimizing the output torque of traveling to wave ultrasonic motor based on multi-objective genetic algorithm. It can effectively improve the output torque of the motor. Firstly, the structure and operation mechanism of the motor is introduced, and the key factors affecting the output torque of the motor is analyzed reasonably;then the parameterized model of the stator of the ultrasonic motor is established by WORKBENCH, the sample points are randomly selected in the design variable space, and the combination of each sample point is obtained. The modal analysis and harmonic response analysis of the stator structure was carried out to establish the response surfaces model of the stator;finally, the global optimal solution was obtained based on the response surface model by using the multi-objective genetic algorithm (MOGA). The results show that the output torque of the ultra-sonic motor can be increased by 8% before and after optimization. © 2023, Beijing Paike Culture Commu. Co., Ltd.

关键词： Stators

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DYNAMIC PRECISION EVALUATION OF COMPENSATED ION-CHAMBERS FOR reactor POWER MONITORING 29

DYNAMIC PRECISION EVALUATION OF COMPENSATED ION-CHAMBERS FOR...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Huang, Qichang Liu, Mingxing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China A College of Computer Sichuan University Chengdu China

ISBN: (纸本)9780791886373

During reactor power monitoring, compensated ion-chambers (CICs) are assembled by two similar gas-filled detectors. The gamma compensation of CICs is essential for detecting precision of thermal neutrons, and requires a pairs of fully matched voltages. Descriptions of detecting precision include current formation model, in which applied voltages and radiation strength act in the process of collecting charged particles. However, the model of CICs are seldom applied in design work to evaluate the monitoring precision. Here we show that imbalance degree of collecting charged particles leads to mismatch of saturation currents depending on difference of recombination and diffusion in each sub-chambers. We analyzed a coaxial type compensated ion-chamber (DL-126), and found that applied voltages and radiation strength have significant impact for ion recombination and electron diffusion. For increasing precision of CICs, this result suggests a dynamic way to evaluate the output deviation using radiation strength. Furthermore, we found the compensation factor of two sub-chambers is only related to the applied voltages and remain unchanged in various radiation. Our results demonstrate how collecting regulars of charged particles are likely to function in setting applied voltages, calculating the charge loss as well as quantifying the saturation currents. We anticipate our analysis to be a starting point for revising detection precision of compensated ion-chambers. For example, evaluating the neutron fluence in the reactor shutdown and restart process, including monitoring task after accident. Furthermore, dynamic precision evaluation of these detectors is a major target of prognostics and health management for Nuclear Instrument. Copyright © 2022 by ASME.

关键词： Ions

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Trusted Algorithm Compiler for Safety I&C Software of NPPs Based on Formal Methods 5th

Trusted Algorithm Compiler for Safety I&C Software of NPPs B...

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

作者： Yang, Fei Lan, Lin Ma, Quan Han, Wen-Xing Liu, Ming-Xing Jiang, Wei Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China Harbin Engineering University Harbin China

ISBN: (纸本)9789811634550

The algorithm for the 1E system of NPPs is generally developed by a graph making tool at the engineering station. After the executable file is generated by the compiler and downloaded to the platform software, the credibility of the executable algorithm depends on the credibility of the generated programming code. Therefore, its security requirements put high demands on the compiler. The formal method has been developed rapidly in response to the problem of trusted compilation in recent years. This paper studies the main methodology and key technological components for designing and implementing the trusted compilers, meanwhile emphasize its industrial application based on existing research. The application is optimized, and a new composite compilation architecture is proposed, which reduces the difficulty of proof work and enhances the flexibility of the compiler’s later phase. Finally, several compiler optimization procedures for the security level software NASPIC are studied, and the algorithm compilation is enhanced, as well as the trusted performance of the device. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Formal verification

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The study of physical characteristics in producing Mo-99

The study of physical characteristics in producing Mo-99

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2018 Transactions of the American Nuclear Society, ANS 2018

作者： Hu, Yuying Luo, Qi Yao, Dong Yu, Yingrui Qiu, Liqing Liao, Hongkuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China Nuclear Power Institute of China Chengdu610041 China

When the velocity of coolant water is 2m/s, 4 targets of 32.5g235U in 3# hole could produce more than 60,000Ci per year. Under this condition, targets are irradiated safely, and the largest production could be gained....

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Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix

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Annals of Nuclear Energy 2025年 222卷

作者： Yiwen Chen Qi Lu Changwen Liu Wei Li Dalin Zhang G.H. Su State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an 710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 61213 China State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an 710049 China

Fully Ceramic Microencapsulated (FCM) fuel, fabricated using 3D printing technology, incorporates traditional Tristructural-Isotropic (TRISO) fuel particles embedded within a 3D-printed SiC matrix. This fuel type shows great potential for compact, high-temperature nuclear reactors. However, comprehensive performance analysis remains challenging due to the multilayered structure, complex material properties, and the irradiation behavior of numerous TRISO particles within the matrix. To address these challenges, this study aims to apply finite element (FE)-based computational homogenization to evaluate the fuel’s thermomechanical properties. First, a detailed finite element analysis (FEA) of a single TRISO particle’s performance was conducted, focusing primarily on the Buffer-IPyC gap size change during irradiation, a critical factor influencing the fuel’s thermal performance. Second, the homogenization of a single TRISO particle was performed using FEA, accounting for the changes in the Buffer-IPyC gap size. Finally, homogenized TRISO particles were randomly distributed and perfectly bonded within a 3D-printed SiC matrix to form a Representative Volume Element (RVE). The FE homogenization of the RVE was then conducted to derive the effective thermomechanical properties of the FCM fuel. The packing fraction of TRISO particles in the matrix ranged from 10 % to 50 %, with temperature and burnup conditions spanning 800–1600 K and 0–16 % FIMA, respectively. Results show that irradiation significantly affects the effective properties of the fuel, though this impact diminishes as burnup increases. Additionally, the effective thermal conductivity of the FCM fuel decreases with increasing TRISO packing fraction, assuming the thermal conductivity of the SiC matrix exceeds that of TRISO particles. This study provides a valuable reference for the design and optimization of FCM fuel for future nuclear applications.

关键词： Thermal conductivity of solids

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