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

作者： Dongliang, Ma Tao, Zhou Bing, Li Yanping, Huang Zejun, Xiao School of Nuclear science and Engineering North China Electric Power University Beijing102026 China Institute of Nuclear Thermal-hydraulic Safety and Standardization North China Electric Power University Beijing102206 China Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy North China Electric Power University Beijing102206 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China HualongPressuried Water Reactor Technology Corporation Ltd. Beijing100037 China

Supercritical water cooled reactor (SCWR) is one of the six types of Generation IV reactor in the international use. For supercritical water cooled reactor, the supercritical water has many peculiar properties near the critical point. During the loss of flow accident, there is a practical significance of carrying out research on the coolant heat load capacity and stability of the flow in the natural circulation loop, which helps to reduce the probability of core meltdown and improve the safety of the reactor. Compared with natural circulation, forced circulation also holds an important position due to its large flow rate in different sizes of the annular channel (resulting in different heat transfer rates). The forced circulation in supercritical water channels is largely based on the experimental data, and the use of CFX software in ANSYS platform provides a model for numerical simulation analysis. Heat transfer was calculated at different annular channel sizes for the supercritical water. Results of the calculation show that a small size of annular pipe channel helps to enhance the heat transfer rates at low pressures. Heat transfer is further strengthened for low heating power and narrow annular channel sizes. The enhancement in heat transfer rate is much more apparent (in small pipes) for larger flow rates. However, there is a corresponding increase in the local eddy viscosity values in annular channels of smaller sizes. © 2016 Association for Computing Machinery Inc. All Rights Reserved.

关键词： Computer software

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Development of high-strength,low-cost wrought Mg–2.0 mass% Zn alloy with high Mn content

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Progress in Natural science:Materials International 2016年第6期26卷 630-635页

作者： Fusheng.Pan Jianjun Mao Gen Zhang Aitao Tang Jia She College of Materials Science and Engineering Chongqing University National Engineering Research Center for Magnesium Alloys Chongqing University Chongqing Research Center for Advanced Materials Chongqing Academy of Science and Technology Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China

Mg–Zn–Mn-based alloys have received considerable attention because of their high creep resistance, strength,and good corrosion resistance. The alloying element Mn in Mg–Zn-based alloys is commonly less than 1 wt%. In the present study, the effect of high Mn content(1 wt% and 2 wt%) on the microstructures and mechanical properties of Mg–2Zn–0.3Sr extruded alloy was investigated. The results revealed that the high Mn content significantly increased the ultimate tensile strength, tensile yield strength, compress yield strength, and yield asymmetry of the alloy without affecting its ductility. The dynamically recrystallized(DRXed) grains of Mg–2Zn–0.3Sr were remarkably refined because of the large amount of fine Mn precipitates in the homogenized alloy. The improved strengths were mainly attributed to the fine DRXed grains according to the Hall–Petch effect and to the large amount of spherical and < 0001 > Mn precipitates through the precipitation and dispersion strengthening. The fine DRXed grains and numerous Mn precipitates effectively suppressed the extension twining, substantially enhanced the compress yield strength, and resulted in improved anisotropy.

关键词： Magnesium alloy Mg–Zn alloy Microstructure Ultra-fine grains Second phase Mechanical properties

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The preliminary performance study of ATF with M3 fuel and Zr-4 cladding 24

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2016 24th International Conference on Nuclear Engineering, ICONE 2016

作者： Chunyu, Yin Teng, Tu Tang, Changbing Jiao, Yongjun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China ChengduSichuan China

ISBN: (纸本)9780791850015

Metal matrix microencapsulated (M3) fuel is one of the research directions on Accident Tolerant Fuel (ATF). In this article, it provides one of ATF design which consists of BISO (Bistructural ISOtropic) particles embedded in a zirconium alloy matrix, and the cladding coating with silicon carbon (SiC). The temperature distribution of the ATF element has been built, and then the center temperature has also been calculated based on the operation parameters of the large-scale pressurized-water reactor. Simultaneity, the several factors of fuel failure is preliminary analyzed and calculated, especially the pressure shell failure mechanism. Copyright © 2016 by ASME.

关键词： Metallic matrix composites

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Neutronic feasibility analysis of fully ceramic microencapsulated fuel for commercial PWRs

Neutronic feasibility analysis of fully ceramic microencapsu...

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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

作者： Mancang, Li Dan, Wang Yingrui, Yu Dong, Qin Wenjie, Li Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9780894487309

The fully ceramic microencapsulated (FCM) fuel is based on tristructural isotropic (TRISO) coated particles embedded in silicon carbide (SiC) matrix, which is among the accident tolerant fuel concept options. With the strength of high fission product retention, the FCM fuel provides potential superior safety performance. Compared to the conventional standard UO2 fuel, the deficiency of FCM fuel is its considerable lower fissile inventory, which results in a reduced reactor power or/and life. Supposing the FCM fuel is used as direct replacement of the fuel in commercial PWRs, the spectrum is softened due to the usage of SiC as matrix, and the moderator temperature coefficient is possible to be positive at the beginning of life, leading to high risk during operation. A neutronic feasibility study of FCM fuel utilized in commercial PWRs is performed in the paper. The fuel enrichment and undermoderated lattice are evaluated by analyzing the typical TRISO particle with UO2 kernels which is widely used in high temperature gas reactors and that with enlarged UN fuel kernels. It was found that under the mandatory constraint of low enriched uranium, the FCM fuel with UO2 kernels, although relatively mature, is only capable of small reactor designs, and the assembly lattice needs to be modified. The FCM fuel with UN kernels, when directly loading in the commercial PWRs, can yield comparable reactor power and life;however, a higher fuel enrichment and the fuel design and fabrication need to be optimized.

关键词： Silicon carbide

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BHEL Smart Wall Blowing System: New Product Development in Manufacturing Industry

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Vikalpa 2021年第4期45卷 240 - 249页

作者： Abhishek Kumar R. Dhanuskodi R. Kaliappan K. Nandakumar Abhishek Kumar teaches design philosophies at Anant National University Ahmedabad. He earned his Ph.D in Management from Pondicherry University. He is an Economics graduate from Calcutta University and MBA from BIM Trichy. He has published more than 20 articles in reputed international journals has authored two books written articles and columns for newspapers and is quoted on issues related to leadership and marketing by various media platforms. His research work comprises construction of brand personality scale for media aesthetics and phenomenological design. His recent publications are on philosophy of a photograph hermeneutic reality of product and on philosophy of intimate spaces. R. Dhanuskodi has nearly 40 years of R&D experience at BHEL India in technical areas applicable for thermal power plants. He is a life member of The Institution of Engineers (India) and The Combustion Institute. He has won two BHEL’s Excel awards under the best author category for technical papers. He has visited France Netherlands and Germany under Indo-Europe Clean Coal Development Program. He has guided 42 UG PG and PhD project works. He holds 11 patents 40 copyrights and 2 design registrations. He has presented papers in 20 conferences and published in 10 national and international journals. R. Kaliappan completed his bachelors in electrical and electronics engineering and Masters in Computer Science. He has 36 years of research experience in different fields of power generation and power plant subsystems such as heat transfer studies on boiler circulation efficiency improvements of boiler subsystems product improvements/ enhancements and setting up test facilities for research studies. He has published a number of technical papers on MHD power generation and heat transfer studies in various national and international journals. He has more than 25 patents and copyrights on products development related to power boilers. He has won BHEL’S gold medal for product development for Smart Wall Blowing system. K. Nandakumar

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Bottom Reflooding Experiments in a Thin Rectangular Channel

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Energy Procedia 2017年 127卷 335-342页

作者： Wei Xu Jun Yao Jianye Ji Xiaojing Liu Xu Cheng Wei Zeng Hongxing Yu School of Nuclear Science and Engineering Shang Hai Jiao Tong University 800 Dong Chuan Road Shanghai 200240 P.R.China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Cheng Du 610041 P.R.China

Experiments were carried out to study the thermal hydraulic behaviors in a narrow rectangular channel under bottom reflooding conditions. The channel is formed between a stainless steel heating plate and a transparent heatproof glass and dimensions of the channel are 600 mm in height, 60 mm in width and 4 mm of gap thickness. All the parameters (such as initial wall temperature, inlet velocity and systematic pressure) affect the heat transfer features during quenching process. The experimental results illustrate that for a given initial surface temperature, rewetting velocity increases with the increasing flow rate and increasing systematic pressure, while it decreases with the increasing initial surface temperature. With different flow rate and system pressure, the rewetting temperature is almost the same, but it varies when initial surface temperature is different.

关键词： Bottom reflooding Rectangular channel Heat tranfer

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A preliminary study on irradiation growth behavior modelling of N36 zirconium alloy tube

A preliminary study on irradiation growth behavior modelling...

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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

作者： Yifei, Miao Yongjun, Jiao Kun, Zhang Shuo, Xing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Nuclear Power Institute of China China

ISBN: (纸本)9780894487309

As a new kind of Zr-Sn-Nb series alloy, N36 has not been explored in irradiation growth behavior before. In this paper, four empirical correlations including power, logarithmic, exponential and hyperbolic tangent law were used to build irradiation growth model of N36 zirconium alloy preliminarily. Before that, lengths of the fuel rods with N36 claddings from poolside measurement were analyzed to get irradiation growth strains, which were then used to fit the four empirical correlations mentioned above. Distribution of fast fluence along axial direction of tubes was considered in all irradiation growth models. The fitting results showed that the hyperbolic tangent law fit irradiation growth strains the best, while power law did the worst. In order to improve the precision of the hyperbolic tangent model, several improvements were done. Verification and validation of the improved hyperbolic tangent irradiation growth model suggested that the size of second phase may have an influence on irradiation growth behavior of N36 tubes.

关键词： Zirconium alloys

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Scaling analysis and SE simulation of the tilted cylinder-interface capillary interaction

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IOP Conference Series: Materials science and Engineering 2018年第1期372卷

作者： S Q Gao X Y Zhang Y H Zhou National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu 610041 China Department of Mechanics and Engineering Sciences College of Civil Engineering and Mechanics Lanzhou University Lanzhou 730000 China

The capillary interaction induced by a tilted cylinder and interface is the basic configuration of many complex systems, such as micro-pillar arrays clustering, super-hydrophobicity of hairy surface, water-walking insects, and fiber aggregation. We systematically analyzed the scaling laws of tilt angle, contact angle, and cylinder radius on the contact line shape by SE simulation and experiment. The following in-depth analysis of the characteristic parameters (shift, stretch and distortion) of the deformed contact lines reveals the self-similar shape of contact line. Then a general capillary force scaling law is proposed to incredibly grasp all the simulated and experimental data by a quite straightforward ellipse approximation approach.

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Preliminary analysis of FCM fuel thermal-mechanical performance under normal and transient conditions

Preliminary analysis of FCM fuel thermal-mechanical performa...

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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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Preliminary analysis of core heat-up for ATFs under accident conditions

Preliminary analysis of core heat-up for ATFs under accident...

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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance

作者： Li, Wei Chen, Ping Su, Guanghui Qiu, Suizheng Tian, Wenxi Li, Wenjie School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan610213 China

ISBN: (纸本)9780894487309

Experience gained in decades of nuclear safety research and previous nuclear accidents direct to the investigation of passive safety system design and accident-tolerant fuel (ATF) system which is now becoming a hot research point in the nuclear energy field. The ATF system is aim at upgrading safety characteristics of the nuclear fuel and cladding in a reactor core where active cooling has been lost, and is preferable or comparable to the conventional UO2-Zr fuel system when the reactor is in normal operation. By virtue of advanced materials with improved basic properties and oxidation resistance, the ATF system is placed high hopes on slowing down the accident progression, allowing wider margin of time for the mitigation measures to be effective. SiC and FeCrAl accident-tolerant claddings and FCM accident-tolerant fuel are considered in this work, as they are receiving more and more attention in China. In this paper, the improved performance of UO2-SiC, UO2-FeCrAl, FCM-SiC and FCM-FeCrAl fuel systems on the core heat-up progress in a pressurized water reactor (PWR) is analyzed by using the best-estimate system code RELAP5 and severe accident analysis program respectively. For this purpose two accident scenarios are selected, e.g., a large break LOCA as a design base accident and an extended station blackout (SBO) severe accident, to reflect the accident-tolerance characteristic of ATFs. Obtained quantitative results show promising safety enhancement in terms of peak cladding temperature (PCT) and recovery of the core coolability for the selected ATF systems, which is beneficial for further down-selections of various kinds of ATF systems.

关键词： Silicon carbide

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