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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 ...

引用

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

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

引用

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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Research on Cylindrical Linear Induction Motor for Drive Mechanism 14

Research on Cylindrical Linear Induction Motor for Drive Mec...

引用

14th International Symposium on Linear Drivers for Industry Applications, LDIA 2023

作者： Niu, Xu Yu, Tianda Zhang, Lu Li, Qingzhao Huang, Siyu Liu, Yanting Wu, Hao Tang, Yuan School of Electrical Engineering Harbin Institute of Technology Harbin China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9798350329612

The control rod drive mechanism (CRDM) is a kind of servo mechanism for the reactor control system of the nuclear power plant. This paper presents a cylindrical linear induction motor suitable for the CRDM. First, the structure of the CRDM is introduced. Second, the relationship between the main dimensions and the electromagnetic load is derived. Third, the influence of materials of the mover shielding shell, speed, and electromagnetic parameters on the lifting force is analyzed by the finite-element method (FEM). Meanwhile, the steady-state temperature of each component of the CRDM is obtained. Finally, a scaled-down prototype is manufactured to verify the rationality of the design. The test results show that the FEM results are consistent with the experimental results, and the essential functions such as lifting, lower insertion, and maintenance can be realized. © 2023 IEEE.

关键词： Finite element method

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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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A review and correlations for two phase flow heat transfer in helically coiled tubes 27

A review and correlations for two phase flow heat transfer i...

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

作者： Ma, Haifu Xu, Tao Li, Peiying Gou, Junli Yuan, Hongsheng Chen, Wei Wu, Yirui Zhong, Mingjun Gao, Yingxian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an710049 China

ISBN: (纸本)9784888983051

Helically coiled heat exchangers have been widely applied in many power conversion systems for their advantages, such as compactness and high efficiency in heat transfer. Reliable heat transfer models are required to analyze the thermal hydraulic characteristics of the once-through helically coiled tube steam generator. The purpose of this study is to evaluate the applicability of the existing heat transfer models. This paper review the experiments for heat transfer in helically coiled tubes in the case of two-phase flow, and summarize and screening corresponding experimental data and correlation. Then, this article compared these correlations to the existing available experimental data to evaluate the applicability of these correlations. Most of the correlations for two phase heat transfer were also valid within the parameter range of pressure, mass flux and heat flux. Results indicate that the currently existing correlation could not accurately match the experiment date. And the Steiner-Taborek correlation was recommended even though the 70% experiment date within the 20% deviation of predicted. Therefore the steam-water two phase flow need to further study to conclude a more suitable correlation in the further. Copyright © 2018-2019 by JSME

关键词： Two phase flow

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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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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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The study of physical characteristics in producing Mo-99

The study of physical characteristics in producing Mo-99

引用

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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Effect of residual pore on the performance of UN kernel TRISO particle fuel 14

Effect of residual pore on the performance of UN kernel TRIS...

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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, Shichao Chen, Ping Zhou, Yi Pang, Hua Xi, Yong Tang, Changbing Zhao, Yanli Qiu, Xi Guo, Zixuan Nuclear power institute of China Science and Technology on Reactor System Design Technology Laboratory Changshun Stress No.1 Chengdu Sichuan610200 China

The thermal-mechanical performance of uranium nitride (UN) tri-isotropic (TRISO) particle with residual pore used in Light Water reactor (LWR) was investigated. The effect of pore size and location on the performance of inner dense pyrolytic carbon (IPyC) layer, SiC layer and outer dense pyrolytic carbon (OPyC) layer was studied. The dimensional changes, fission gas release and internal pressure of the fuel particle layers were calculated. Residual pore size can affect the stress distribution of coated layers obviously. The residual pore especially the big ones may be the source of cracks on the SiC layer, which can break or loss the capacity of SiC layer. Residual pore location has little influence on the stress distribution of the coated layer. In order to maintain the fission retention capacity of TRISO particle, the big residual pore should be avoided during fabrication process. Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water reactor Fuel Performance *** rights reserved.

关键词： Silicon carbide

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