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2017 Transactions of the American Nuclear Society, ANS 2017

作者： Wu, Wenbin Yu, Yingrui Li, Qing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

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Preliminary evaluation of U 3 Si 2 -FeCrAl fuel performance in light water reactors through a multi-physics coupled way

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Nuclear Engineering and design 2018年 328卷 27-35页

作者： Yanan He Ping Chen Yingwei Wu G.H. Su Wenxi Tian Suizheng Qiu Shaanxi Engineering Research Center of Advanced Nuclear Energy School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an City 710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China

U 3 Si 2 -FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physic fuel performance code called BEEs for LWR fuels has been developed based on Multiphysics Object-Oriented Simulation Environment (MOOSE) using the Object-Oriented Programming (OOP) method. As a first step to verify the capability of BEEs, one problem has been conducted using BEEs and compared with the results from BISON and ABAQUS. Then, the most recently available U 3 Si 2 -FeCrAl behavior models have been coded in BEEs. Fuel performance analysis was conducted for U 3 Si 2 -FeCrAl fuel system using BEEs and comparisons with UO 2 -Zr4 and U 3 Si 2 -Zr4 were made in this work. The results show that U 3 Si 2 -FeCrAl fuel system can lower the fuel peaking temperature about 300 K and have flat radial temperature distribution which can mitigate or eliminate the fuel cracking during power up. Further, the pellet-cladding mechanic interaction can be delayed or fully eliminated employing U 3 Si 2 -FeCrAl fuel system in light water reactors (LWRs).

关键词： U 3 Si 2 Multiphysics Fuel performance MOOSE BEEs

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The study on overall I&C system scheme for floating nuclear power plant ACP100S and ACP25S 10

The study on overall I&C system scheme for floating nuclear ...

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10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017

作者： Chen, Zhi Long-Tao, Liao Dan-Rong, Song You, Kai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9781510851160

Floating nuclear power plant (FNPP) is built on the offshore platform and it is defined as a kind of Small and Modular reactor(SMR) due to its power level. The FNPP can provide power supply, fresh water and high temperature steam and other products. So it can be used as special energy sources, such as regional power supply, district heating and offshore oil exploitation. At present, two types of FNPP, named ACP100S and ACP25S, are developed by China national Nuclear Corporation (CNNC). In this paper, the overall technical parameters and overall technical scheme of ACP100S and ACP25S are introduced firstly. On the basis of these schemes, the different arrangements of nuclear power plant which are used for meeting the different energy demands are discussed. Due to the different configuration of nuclear power plant, the requirements for the Instrument and Control (I&C) system are different, so the paper discusses some overall configurations of I&C system under the several typical arrangements models, i.e., the single reactor and the single turbine, the double reactors and double turbines, and the double reactors and the single turbine. Furthermore, the characteristics of these overall I&C configurations are analyzed. © 2017 Westinghouse Electric Company LLC. All Rights Reserved.

关键词： Nuclear power plants

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Elastic and plastic analysis of O-ring seal for reactor pressure vessel 13th

Elastic and plastic analysis of O-ring seal for reactor pres...

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13th Asia-Pacific Symposium on Engineering Plasticity and its Applications, AEPA 2016

作者： Shao, Xuejiao Zheng, Liangang Zhang, Liping Fu, Xiaolong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9783035710243

The elasto-plastic analysis for reactor Pressure Vessel seal is necessary because of nuclear safety is actively demanded. The existed work based on simplified way to simulate the seal ring, such as uniform stress, spring elements, is too conservative. Therefore, it is necessary to simulate seal ring using 3D solid model considering the elasto-plastc deformation. In this paper, the two-dimensional model is adopted to simulate the compressing and springback character of inconel 718 O-ring using nonlinear isotropic hardening constitutive model and contact algorithm. The simulation approach and constitutive model are validated according to the deformation of seal ring using ANSYS. The seal analysis for reactor pressure vessel is achieved by considering complex loads, such as bolt pre-tightening force and temperature/pressure transient with the usage of an elasto-plastic constitutive model. It is found that the deformation of seal ring obtained by finite element is close to true value. The application of 3D solid model can reduce excessive conservatism effectively and improve the precision of seal analysis compare to the simplified method. © 2017 Trans Tech Publications, Switzerland.

关键词： O rings

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The CFD calculation of a stratification break-up test of light gas in a closed vessel

The CFD calculation of a stratification break-up test of lig...

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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017

作者： Yazhe, Lu Yu, Zhang Xu, Ran Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9784890471676

During the course of a hypothetical severe accident in a light water reactor, spray systems could be used in the containment in order to prevent overpressure in case of a steam line break and to enhance the gas mixing in case of the presence of hydrogen. Thus these two effects induced by spray might compete with each other having an influence on the hydrogen risk. Focusing on the dynamic effect of spray, the impact of spray on the breakup of a light gas layer in a closed vessel is simulated and the experimental test evaluated here is TOSQAN 113 test that belongs to the dynamic part of SARNET FP6 benchmarks. ANSYS FLUENT 14.5 is chosen for the simulation tool and spray droplets are tracked with using the Euler-Lagrange approach-Discrete Phase Model (DPM). The code validation and several sensitivity studies are done to sum up the basic method of numerical simulation of spray with CFD code and assess the influence of calculation settings and parameters, such as turbulence model and spray boundary condition. The code validation shows that the results of calculations acceptably agree with the experimental data and the sensitivity studies reveal that spray boundary condition is a rather important factor for the accuracy of simulation. Conclusion gained in from the present work can provide some reference of the numerical analysis of containment.

关键词： Boundary conditions

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SMR built-in pressurizer operation transients analysis

SMR built-in pressurizer operation transients analysis

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2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017

作者： Songwei, Li Yu, Liu Xi, Chen Zhongchun, Li Danrong, Song Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9784890471676

Three primary design principles, meanwhile the design features, are carried through the R&D process of Chinese Small Module reactor (ACP100): integral layout, compact design and modularized configuration. As a substantial demonstration of the above design conceptions, an upper plenum built-in pressurizer is proposed for the pressure control system design for Chinese SMR. In this design, branches with large diameters connected to the primary loop (i.e. surge line, etc.) are eliminated, and this will significantly reduce the LOCA possibility due to the pressure boundary breach. This study mainly focuses on the feature of responses of the built-in pressure control system during the system transients, such as step load increase/decrease, ramp load increase/decrease and partial loss of electrical load. Initial status of the plant, assumptions, postulated transient condition and methodology of this analysis are described in the first section. Important thermal hydraulic parameters that can picture the transient characteristics of the coolant system are given in the second section. It shows that, during those transients, no reactor safety related signals or safety guard features are triggered or actived. It also shows that Nuclear/thermal power response rapidly and stably, and average coolant temperature and system pressure are welled controlled within the range of normal deviation of the set point values of safety related system. This study results get a good agreement with the operating experiment study of the build-in pressure control system.

关键词： Transient analysis

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Computation of fluid thrust force from the pressure release tank of nuclear power plant pressurizer 17

Computation of fluid thrust force from the pressure release ...

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17th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2017

作者： Xiong, Fu-Rui Jiang, Nai-Bin Wu, Ge Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

Pressure release tank is a key component of nuclear power plant safeguard. Evaluating the fluid thrust force from high pressure and high temperature flow jet under postulated accidents is an essential task for nuclear system design and safety estimation. In this work, flow jet impingement from pressure release tank to nearby building roof is computed via a two-stage strategy. First, the RELAP5 code is applied to estimate thermal-hydraulic conditions at pressure release tank outlet. The thermal-hydraulic computational model includes key components of pressure release tank and its connection to the pressurizer. Based upon the thermal-hydraulic estimation within the pressure release tank, detailed computational fluid dynamics (CFD) simulation is performed with full considerations of how flow thrust is applied on nearby structures. The two-stage computational strategy provides a practical paradigm for fluid thrust force estimation. © 2016 Association for Computing Machinery Inc. All Rights Reserved.

关键词： Computational fluid dynamics

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A study on the sealing behaviors of the laterally one side restrained C-ring under internal pressure by numerical simulation 25

A study on the sealing behaviors of the laterally one side r...

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2017 25th International Conference on Nuclear Engineering, ICONE 2017

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

ISBN: (纸本)9784888982566

C-ring, which is one of the main sealing elements of reactor Pressure Vessels, is composed of a close-wound helical spring surrounded by two metal linings. C-ring has better resilience and sealing characteristics. Just because of the complex structure of C-ring, it was studied by experiments almost. There were also some numerical simulations on C-ring. With these methods, the compression-decompression process of C-ring under ideal condition can be simulated. But them cannot be used to study the sealing behavior of laterally one side restrained C-ring under internal pressure, which is fit for practical condition. This paper will establish a 3D numerical simulation method to study the C-ring which is mentioned as above. In this paper, it can be obtained that with internal pressure forcing and sealing groove squeezing, sealing performance of C-ring will reduce;when p>20MPa, the ratio of reducing becomes bigger;when p>140MPa, it will generate leakage;inner lining and outer lining will generate biggish plastic deformation, while the stress distribution in spring changes much. © Copyright 2017 ASME.

关键词： Numerical methods

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A Dual-Band Multilayer Heterogeneous Frequency Selective Surface with Miniaturized Unit Cell

A Dual-Band Multilayer Heterogeneous Frequency Selective Sur...

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2018 IEEE International Conference on Computational Electromagnetics, ICCEM 2018

作者： Cui, Yichun Zhang, Shengjun Liu, Jiaqi Liu, Xin Xue, Hui Zhang, Borong National Key Laboratory of Science and Technology on Test Physics and Numerical Mathematics Beijing100076 China Beijing Institute of System Engineering Beijing China Beijing Institute of Astronauctical Systems Engineering Beijing100076 China

ISBN: (纸本)9781538612415

In terms that most researches about Frequency Selective Surface (FSS) concentrate on single layer structure design or FSS with one fundamental mode, a multilayer heterogeneous dual-band frequency selective surface composed of slot FSS, dielectric medium, patch FSS is proposed. This FSS possess miniaturized unit cell with dimension of 6× 6mm2, it acts as a dual-band filter in given bands while behaving as an entire reflector in others. Results show that this dual-band frequency selective surface has narrow transmission bandwidths near 8.5GHz and 19.5GHz and flat rejection bands except for that. The structure exhibits excellent stability for oblique incident angles and provides polarization-independent response with compact design which moves the operating bands away from grating lobes. A method to adjust the element's size is proposed as well based on basic elements when given pass band frequency changed. © 2018 IEEE.

关键词： Frequency selective surfaces

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designing Cation–Solvent Fully Coordinated Electrolyte for High-Energy-Density Lithium–Sulfur Full Cell Based On Solid–Solid Conversion

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Angewandte Chemie 2021年第32期133卷

作者： Huijun Yang Dr. Yu Qiao Dr. Zhi Chang Prof. Ping He Prof. Haoshen Zhou Energy Technology Research Institute National Institute of Advanced Industrial Science and Technology (AIST) 1-1-1 Umezono Tsukuba 305-8568 Japan Graduate School of System and Information Engineering University of Tsukuba 1-1-1 Tennoudai Tsukuba 305-8573 Japan Center of Energy Storage Materials & Technology College of Engineering and Applied Sciences Jiangsu Key Laboratory of Artificial Functional Materials National Laboratory of Solid State Micro-structures Collaborative Innovation Center of Advanced Micro-structures Nanjing University Nanjing 210093 P. R. China

Sulfur chemistry based on solid–liquid dissolution-deposition route inevitably encounters shuttle of lithium polysulfides, its parasitic interaction with lithium (Li) anode and flood electrolyte environment. The sulfurized pyrolyzed poly(acrylonitrile) (S@pPAN) cathode favors solid-solid conversion mechanism in carbonate ester electrolytes but fails to pair high-capacity Li anode. Herein, we rationally design a cation-solvent fully coordinated ether electrolyte to simultaneously resolve the problems of both Li anode and S@pPAN cathode. Raman spectroscopy reveals a highly suppressed solvent activity and a cation-solvent fully coordinated structure (molar ratio 1:1). Consequently, Li electrodeposit evolves into round-edged morphology, LiF-rich interphase, and high reversibility. Moreover, S@pPAN cathode inherits a neat solid-phase redox reaction and fully eliminated the dissolution of lithium polysulfides. Finally, we harvest a long-life Li-S@pPAN pouch cell with slight Li metal excessive (0.4 time) and ultra-lean electrolyte design (1 μL mg S −1 ), delivering 394 Wh kg −1 energy density based on electrodes and electrolyte mass.

关键词： high-energy-density lithium-sulfur battery metal-organic framework (MOF) S@pPAN cathode solid-solid conversion

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