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16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015

作者： Zhuohua, Zhang Shinian, Peng Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

ISBN: (纸本)9781510811843

According to former study on oxygen diffusion, Nb-Zr solid reaction and Uo2-zr solid reaction, models of oxidation, solid reaction in fuel meat and relocation of molten fuel meat are developed based on structure and material properties of Uo2-zr plate. The new models can supply theoretical elements for safety analysis of core assembled with dispersion plate-type fuel under severe accident.

关键词： Uranium dioxide

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On the degradation of the effectiveness of nonlinear diffusion acceleration with parallel block jacobi splitting

On the degradation of the effectiveness of nonlinear diffusi...

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2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016

作者： Schunert, Sebastian Wang, Yaqi Ortensi, Javier Gleicher, Frederick Baker, Benjamin DeHart, Mark Martineau, Richard Thermal Science and Safety Analysis Idaho National Laboratory Idaho FallsID United States Reactor Physics Analysis and Design Idaho National Laboratory Idaho FallsID United States Nuclear Science and Technology Modeling and Simulation Idaho National Laboratory Idaho FallsID United States

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Robust guided image filtering

arXiv

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arXiv 2017年

作者： Liu, Wei Chen, Xiaogang Shen, Chunhua Yu, Jingyi Wu, Qiang Yang, Jie Key Laboratory of Ministry of Education for System Control and Information Processing Shanghai Jiao Tong University Shanghai200240 China College of Communication and Art Design University of Shanghai for Science and Technology Shanghai200093 China School of Computer Science University of Adelaide AdelaideSA5005 Australia College of Engineering University of Delaware NewarkDE19176 United States School of Computing and Communications University of Technology SydneyNSW2007 Australia

The process of using one image to guide the filtering process of another one is called Guided Image Filtering (GIF). The main challenge of GIF is the structure inconsistency between the guidance image and the target image. Besides, noise in the target image is also a challenging issue especially when it is heavy. In this paper, we propose a general framework for Robust Guided Image Filtering (RGIF), which contains a data term and a smoothness term, to solve the two issues mentioned above. The data term makes our model simultaneously denoise the target image and perform GIF which is robust against the heavy noise. The smoothness term is able to make use of the property of both the guidance image and the target image which is robust against the structure inconsistency. While the resulting model is highly non-convex, it can be solved through the proposed Iteratively Re-weighted Least Squares (IRLS) in an efficient manner. For challenging applications such as guided depth map upsampling, we further develop a data-driven parameter optimization scheme to properly determine the parameter in our model. This optimization scheme can help to preserve small structures and sharp depth edges even for a large upsampling factor (8× for example). Moreover, the specially designed structure of the data term and the smoothness term makes our model perform well in edge-preserving smoothing for single-image tasks (i.e., the guidance image is the target image itself). It performs well in several challenging applications in avoiding halos, gradient reversals and properly preserving edges with noise/texture being well smoothed. Through extensive experimental results, we show that the proposed RGIF can have promising performance in many applications such as guided depth map upsampling, flash/no flash filtering, detail enhancement, HDR tone mapping, structure smoothing and clip-art JPEG compression artifact removal. This paper is an extension of our previous work [1], [2]. Copyright © 2017, T

关键词： Image enhancement

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Derivation of the point-kinetics parameters for the coupled reactors

Derivation of the point-kinetics parameters for the coupled ...

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2016 Transactions of the American Nuclear Society, ANS 2016

作者： Wang, Yaqi Schunert, Sebastian Ortensi, Javier Gleicher, Frederick Baker, Benjamin Youinou, Gilles Dehart, Mark Martineau, Richard Idaho National Laboratory Nuclear Methods Development Idaho FallsID United States Idaho National Laboratory Reactor Physics Analysis Design Idaho FallsID United States Idaho National Laboratory Nuclear Science Technology Modeling and Simulation Idaho FallsID United States

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Development and verification of SNTA code system for SCWR core steady state analysis 23

Development and verification of SNTA code system for SCWR co...

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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015

作者： Wang, Lianjie Zhao, Wenbo Yang, Ping Ma, Yongqiang Lu, Di Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydraulic sub-channel code. The problem of CSR1000 core is studied to verify SNTA. The results calculated by SNTA are agreed well with those by CASIR and SRAC. SNTA is more efficient than CASIR and SRAC whose neutronics modules are based on the Finite Difference Method. The numeric results show that SNTA can be well applied to SCWR core steady state analysis and core concept design. Copyright © 2015 by JSME.

关键词： Finite difference method

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Simulation of esprit of hualong secondary passive residual heat removal system by using relap5 16

Simulation of esprit of hualong secondary passive residual h...

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16th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2015

作者： Feng, Li Science and Technology on Reactor System Design Technology Laboratory ChangShun Avenue 328 ShuangLiuCounty ChengDu China

ISBN: (纸本)9781510811843

A 3rd generation reactor called HuaLong is developed by China National Nuclear Corporation (CNNC). S econdary passive system (PRS) is designed to remove the residual heat during 72 hours after the reactor trips. To verify the ability of PRS system, the test facility ESPRIT is built in Chengdu which is 1:1 in heigh t and 1/62.5 in power. Tests are consisted by three Steady-states and one transient. One model of RELAP5 mod3.2 is developed and used to simulate the steady and transient tests. The results of RJELAP5 show con sistent with facility results, but the early phenomenon during transients is different between RELAP5 and tests as RELAP5 underestimates the direct-contact condensation power.

关键词： Condensation

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Observability-driven Sensor Deployment in Smart Academic Environments: Demo Abstract 16

Observability-driven Sensor Deployment in Smart Academic Env...

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Proceedings of the 14th ACM Conference on Embedded Network Sensor systems CD-ROM

作者： A. Agarwal K. Jaiswal U. Gudhaka V. Munigala Krithi Ramamritham Gopinath Karmakar Department of Computer Science & Engineering Indian Institute of Technology Bombay Reactor Control System Design Section Bhabha Atomic Research Centre

ISBN: (纸本)9781450342636

Saving energy without causing discomfort and without demanding human intervention is the need of the day. It is important to develop sensor systems which not only satisfy user requirements, but also take energy consumption into consideration. In this demo, we present the sensing subsystems of a Smart Academic Environment, based upon the core concept of 'Observability' [1] which -- while satisfying user needs -- helps to reduce the number of sensors required.

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The instrumentation and control system for small modular reactor ACP100 9

The instrumentation and control system for small modular rea...

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9th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2015

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

ISBN: (纸本)9781510808096

The small modular reactor (SMR), which is coded ACP100 and developed by China National Nuclear Corporation(CNNC), is an innovative PWR based on existing PWR technology, adapting "passive" safety system and "integrated" reactor design technology. It can reach large power by several modular combinations and can be used in different places and different condition. This paper introduces the main technical characteristic of ACPI00 firstly, for example, integrated layout of primary system and equipment, larger primary coolant inventory, once-through steam generator (OTSG), complete passive safety systems, multi-unit layout, and so on. Based on the description of the main technical characteristic of the ACPI00, the basic design rules and requirements for the ACPI00 instrumentation and control (I&C) system are introduced in this paper. The overall I&C system architecture is also introduced. Especially, the design scheme and features of the NSSS I&C systems, including reactor power control system, OTSG feedwater control system, reactor protection system, in-core instrumentation system, ex-core neutron flux monitoring system, are discussed in this paper. Furthermore, the simulation studies for the main control systems are introduced in the paper, including simulation method, simulation models and simulation results. The control scheme of these control systems are validated by the simulation study.

关键词： Pressurized water reactors

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Numerical simulation of sealing behavior of C-ring for reactor Pressure Vessel 23

Numerical simulation of sealing behavior of C-ring for React...

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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015

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

ISBN: (纸本)9784888982566

C-ring, whose sealing behavior is the key to the sealing structure, is one of the main seal-rings for reactor Pressure Vessel. A finite element model with less simplification has been established using ANSYS APDL to simulate the sealing behavior of C-ring. The numerical results, including sealing behavior curve, specific pressure and springback value, have been compared with test results at 7.67%, 8.42% and 8.09% compression ratios respectively. It confirms the validity of this numerical simulation method. With the numerical method, the deformation and stress distribution and sealing behavior curve of C-ring can be obtained. The behavior curve can be divided into 5 sections. At 10% compression ratio, the peak contact stress is 501MPa, the contact width is 3.22mm, the total springback value is 0.460mm, the effective springback value is 0.332mm and the linear load is 788N/mm. As C-ring is composed of three parts, three models, i.e. spring-only, spring with inner lining and spring with two linings, have been simulated to study the effect of the contact states between each parts on sealing behavior. Copyright © 2015 by JSME.

关键词： Numerical models

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Study on hydrogen flame acceleration and ddt properties at elevated temperatures and pressures 23

Study on hydrogen flame acceleration and ddt properties at e...

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23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015

作者： Peng, Huanhuan Yu, Hongxing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9784888982566

Hydrogen security is an important problem of the severe accident analysis in NPP, and the security of hydrogen detonation is more important. The hydrogen risk mainly focused on the risk of flame acceleration (FA) and deflagration-to-detonation transition (DDT) processes. As the processes involved in combustion and detonation are quite complex, it is difficult to present a detailed description of the whole process. Based on the physical phenomena of flame acceleration, the present paper brief introduces two criteria for hydrogen security analysis of detonation, which are FA σ criteria and DDT λ criteria. From the present paper, effect of initial pressures and temperatures on FA and DDT has been discussed. It describes the limit condition of flame acceleration by the quench/re-ignition of flammable gas mixture theory. So as to promote the flame acceleration criteria at elevated temperatures and pressures from the former one. Last the application for hydrogen safety analysis in GASFLOW code has been recommended. Copyright © 2015 by JSME.

关键词： Combustion

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