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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

作者： Li, Wenjie Tang, Changbing Liu, Zhenhai Li, Wei Chen, Ping Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Design Sub-institute Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9780894487309

FCM fuel is a candidate fuel form to replace commercial UO2 fuel rod in LWR to enhance fuel reliability under accident conditions. The FCM pellet consists of TRISO particles embedded inside the dense SiC matrix. This fuel design is more complex than conventional LWR fuel, which needs new fuel performance models or analysis tools to assist fuel design and concept evaluation. In this paper an attempt was made to develop a finite element method to analyze FCM fuel pellet thermal-mechanical performance. Three idealized cases of normal operation, power ramp, and LOCA were analyzed. The results showed that the temperature distribution and stress distribution of FCM pellet exhibited a strong non-uniformity. The irradiation strain and creep of buffer layer and PyC layers had a strong effect on the mechanical performance of FCM pellet. The hoop stresses of SiC layers and SiC matrix increased significantly during the LOCA and varied with radial positions.

关键词： Finite element method

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A Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC 23rd

A Monte Carlo Code Developed for Radiation Shielding Calcula...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Ying, Dongchuan Lyu, Huanwen Tang, Songqian Shang, Xiaotong Xiao, Feng National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610041 China Department of Engineering Physics Tsinghua University Beijing100084 China

ISBN: (纸本)9789811988981

In this paper, a new developed Monte Carlo method code, intended to be used in shielding calculations, will be introduced. This code was developed on the basis of RMC and under the collaboration of the Nuclear Power Institute of China and Tsinghua University. To meet the requirement of shielding calculations, many features or functions have been realized, such as the flexible fixed source definition and calculation, the gamma transport function, variance reduction function and various tally functions, etc. Those functions have enabled the new version of RMC to have the radiation shielding capability. The validation and application of radiation shielding calculation capability have been carried out. The results of a nuclear power plant pressurized water reactor model will be presented and good agreements have been achieved, which proves the capability of the RMC in the shielding calculations. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Pressurized water reactors

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A Method for Generating Set of Test Cases for Nuclear Power DCS Combination Based on Contract Model 6th

A Method for Generating Set of Test Cases for Nuclear Power ...

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6th International Conference on Computing, Control, and Industrial Engineering, CCIE 2021

作者： Peng, Beicheng Chen, Zhi Liu, Jie Liu, Zhaojun Computer School University of South China Hengyang421001 China National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811939266

Aiming at the need to solve the problem of complex interaction of parameters and difficulty in determining the combination strength in the combination test of the digital I&C system of nuclear power plants, a method for generating a set of variable strength combination test cases based on a contract model is proposed. First, analyze the relationship between input parameters and output parameters from the constructed contract model, determine the actual interaction relationship of the system, and adopt the variable strength combination test case generation method based on the In-Parameter-Order strategy to achieve full coverage of the actual interaction relationship between components, and use contractual constraints to further reduce the scale of test data. Finally, the algorithm is applied to the test of nuclear power plant core temperature measurement system. The results show that the proposed algorithm has certain advantages in test data scale, coverage and error detection ability. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Modeling and Analysis of Novel Integrated Radial Hybrid Magnetic Bearing for Magnetic Bearing Reaction Wheel

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Chinese Journal of Mechanical Engineering 2010年第5期23卷 655-662页

作者： HAN Bangcheng Key Laboratory of Novel Inertial Instrument ＆ Navigation System Technology of Fundamental Science for National Defense Beihang University Beijing 100191 China School of Instrument Science and Opto-electronics Engineering Beihang University Beijing 100191 China

Conventional ball bearing reaction wheel used to control the attitude of spacecraft can＇t absorb the centrifugal force caused by imbalance of the wheel rotor,and there will be a torque spike at zero speed,which seriously influences the accuracy and stability of spacecraft attitude *** with traditional ball-bearing wheel,noncontact and no lubrication are the remarkable features of the magnetic bearing reaction wheel,and which can solve the high precision problems of *** general,two radial magnetic bearings are needed in magnetic bearing wheel,and the design results in a relatively large axial dimension and smaller momentum-to-mass *** this paper,a new type of magnetic bearing reaction wheel（MBRW） is introduced for satellite attitude control,and a novel integrated radial hybrid magnetic bearing（RHMB） with permanent magnet bias is designed to reduce the mass and minimize the size of the MBRW,*** equivalent magnetic circuit model for the RHMB is presented and a solution is *** stiffness model is also presented,including current stiffness,position negative stiffness,as well as tilting current stiffness,tilting angular position negative stiffness,force and moment equilibrium *** design parameters of the RHMB are given according to the requirement of the MBRW with angular momentum of 30 N ？ m ？ s when the rotation speed of rotor reaches to 5 kr/*** nonlinearity of the RHMB is shown by using the characteristic curves of force-control current-position,current stiffness,position stiffness,moment-control current-angular displacement,tilting current stiffness and tilting angular position stiffness considering all the rotor position within the clearance space and the control *** proposed research ensures the performance of the radial magnetic bearing with permanent magnet bias,and provides theory basis for design of the magnetic bearing wheel.

关键词： magnetic bearing reaction wheel radial hybrid magnetic bearing equivalent magnetic circuit current stiffness position negative stiffness tilting current stiffness tilting angular position stiffness

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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 ...

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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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Vibration absorption of parallel-coupled nonlinear energy sink under shock and harmonic excitations

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Applied Mathematics and Mechanics(English Edition) 2021年第8期42卷 1135-1154页

作者： Jian’en CHEN Wei ZHANG Jun LIU Wenhua HU Tianjin Key Laboratory for Advanced Mechatronic System Design and Intelligent Control School of Mechanical EngineeringTianjin University of TechnologyTianjin 300384China National Demonstration Center for Experimental Mechanical and Electrical Engineering Education Tianjin University of TechnologyTianjin 300384China Beijing Key Laboratory of Nonlinear Vibrations and Strength of Mechanical Structures College of Mechanical EngineeringBeijing University of TechnologyBeijing 100124China

Nonlinear energy sink(NES)can passively absorb broadband energy from primary *** multiple NESs connected in parallel exhibit superior performance to single-degree-of-freedom(SDOF)*** this work,a linear coupling spring is installed between two parallel NESs so as to expand the application scope of such vibration *** vibration absorption of the parallel and parallel-coupled NESs and the system response induced by the coupling spring are *** results show that the responses of the system exhibit a significant difference when the heavier cubic oscillators in the NESs have lower stiffness and the lighter cubic oscillators have higher ***,the efficiency of the parallel-coupled NES is higher for medium shocks but lower for small and large shocks than that of the parallel *** parallel-coupled NES also shows superior performance for medium harmonic excitations until higher response branches are *** performance of the parallel-coupled NES and the SDOF NES is *** is found that,regardless of the chosen SDOF NES parameters,the performance of the parallel-coupled NES is similar or superior to that of the SDOF NES in the entire force range.

关键词： coupling influence nonlinear energy sink(NES) vibration absorption

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Hydrogen risk analysis of a large pressurized water reactor using hydragon code 27

Hydrogen risk analysis of a large pressurized water reactor ...

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

作者： Zhang, Xiaolong Yu, Jiyang Huang, Tao Jiang, Guangming Zou, Zhiqiang Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888983051

This paper presents the hydrogen risk analysis of a large Pressurized Water reactor (PWR) undergoing a severe accident using the HYDRAGON code. The code has been developed by the Department of Engineering Physics, Tsinghua University, as a hydrogen risk analysis software specialized for containment building of nuclear reactor power plants. The chemical interaction between zirconium cladding of the fuel rods and overheated coolant may release hydrogen when severe accidents occur in PWRs. The hydrogen mixed with air existing in containment may jeopardize the integrity of containment building if the flammable mixture explodes. In order to mitigate the hydrogen risk, many nuclear power plants install the Passive Autocatalytic Recombiners (PARs) that allow hydrogen and oxygen react chemically at low temperature without any sights of flame. Recombiners remove hydrogen and thereby prevent explosions. This work simulated the gas diffusion behaviors during the accident in the containment of a large PWR. The simulations obtained spatial concentration distribution of various gas species including hydrogen, oxygen, steam and nitrogen and several key parameters that are required to complete hydrogen burning and explosion investigation. Sensitivity analyses of recombiners' quantity and positions and hydrogen discharge intensity provides the reference for hydrogen mitigation measure design in the containment. The results demonstrate that the number of recombiners rather than positions has stronger influences on hydrogen mitigation. Since the installation position reflects less sensitivity, the recombiners could be arranged as higher as possible if necessary. Copyright © 2018-2019 by JSME

关键词： Hydrogen

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STARTUP ANALYSES OF A HELIUM-XENON GAS-COOLED reactor 30

STARTUP ANALYSES OF A HELIUM-XENON GAS-COOLED REACTOR

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Ma, Yugao Bao, Hui Lu, Jiahao Ding, Shuhua Zhang, Meng Yang, Xiaolong Deng, Jian Zhang, Muhao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China College of Nuclear Technology and Automation Engineering Chengdu University of Technology Chengdu610059 China

ISBN: (纸本)9784888982566

The Helium-Xenon (He-Xe) gas-cooled reactor uses a He-Xe gas mixture to remove the heat from the reactor core. It has the characteristics of a long life-cycle, simple operation, and high power-mass ratio, which has an excellent application prospect in the field of Space reactors Power systems. The high operation temperature distinguishes the He-Xe gas-cooled reactor from the traditional reactor in reactivity feedback characteristics. Except for the Doppler effect of the fuel and monolith, the thermal expansion also introduces reactivity feedback during reactor operation. In this work, reactivity feedback characteristics, steady-state characteristics, and transient characteristics of a hundred-kilowatt-level He-Xe gas-cooled reactor (Submersion-Subcritical Safe Space reactor, S4) were analyzed. The Doppler feedback characteristics and thermal expansion feedback coefficients of fuel, matrix, and reflector from the cold to the hot state of the S4 reactor core were calculated based on the reactor Monte Carlo code (RMC). The results show that the S4 reactor core is mainly affected by the fuel Doppler effect and the matrix thermal expansion effect. Furthermore, the temperature distributions of fuel and He-Xe gas of the S4 reactor were calculated using the He-Xe reactor transient analysis code (HXRTRAN). The transient characteristics of the S4 reactor core when different reactivity was introduced were analyzed. This study may provide a reference for the operation state of the He-Xe gas-cooled reactor. © 2023 by JSME.

关键词： Helium

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Phase-Field Modelling of Void Evolution in Binary Alloys Under Irradiation

Phase-Field Modelling of Void Evolution in Binary Alloys Und...

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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023

作者： Lu, Yong Yang, Yuhang Li, Wenjie Sun, Dan Liu, Xingjun Wang, Cuiping College of Materials and Fujian Key Laboratory of Surface and Interface Engineering for High Performance Materials Fujian Xiamen China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789819971565

The formation and growth of voids have significant influence on the dimensional changes of nuclear materials subjected to irradiation. In this paper, we developed a phase-field model to investigate the evolution of voids in binary alloys under irradiation, which includes the process of irradiation-induced defect formation and annihilation. The relationship of alloy composition and defect formation energy was determined. The nucleation and growth of voids for various alloy compositions were simulated to investigate the effect of solute composition on the void growth kinetics. Our simulation results indicate that, the composition of matrix phase and its influence on the formation energy of vacancy are essential for the growth kinetics and void distribution during irradiation. As an example, the void nucleation and growth in U-Zr alloys are also studied and consistence between the present results and experimental observations were obtained. © The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd 2024.

关键词： Binary alloys

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Simulation and Calculation of Proximity Effect of Coils under Fast Transients 13

Simulation and Calculation of Proximity Effect of Coils unde...

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13th Asia-Pacific International Symposium on Electromagnetic Compatibility and Technical Exhibition, APEMC 2022

作者： Wang, Zongyang Song, Wenchang Xie, Yanzhao He, Xianjian Xi'An Jiaotong University State Key Laboratory of Electrical Insulation and Power Equipment School of Electrical Engineering Xi'an China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (数字)9781665416719

ISBN: (纸本)9781665416719

Proximity effect over a broad frequency range plays an important role in analyzing transients in the coils. The frequency dependent characteristic makes proximity effect a tricky problem. This paper first introduces FEM simulation to calculate the complex impedance of proximity effect and compares different axial arrangement of two conductors, shows a good agreement. In addition, different formulas are used to compare their results with FEM simulation to verify their accuracy. Kane formula and Modified formula can both get relatively accurate results. Considering the accuracy and conciseness of Modified formula, it is preferred in the analysis of transients in coils. © 2022 IEEE.

关键词： Finite element method

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