The Experts below are selected from a list of 264 Experts worldwide ranked by ideXlab platform
B.m. Girish - One of the best experts on this subject based on the ideXlab platform.
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Corrosion behaviour of Lead Alloy/zircon particulate composites
Corrosion Science, 1997Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract A study of the corrosion behaviour of Lead Alloy matrix composites containing varying amounts of zircon particles shows that the corrosion resistance of the composites decreases with increase in zircon content. However, heat treatment at 200 °C for up to 5 h seems to improve the corrosion resistance. An attempt is made in the paper to explain these phenomena.
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Mechanical properties of Lead Alloy based composite materials for battery applications
1996Co-Authors: Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:The present paper is a report of an investigation made into the mechanical properties of Lead Alloy composite materials reinforced with two different ceramic particles namely zircon and Sic. The Lead-antimony Alloy(Lead 80% and antimony 20%)was used as the base matrix Alloy in either case. The composite materials were fabricated using vortex method by dispersing the ceramic particles from 1 to 5 percent by weight in steps of 2% into the molten Lead Alloy above the liquidus temperature. The size of the part-icles used was 90 to 150 um in either case. The influence of the two dispersoids on the properties on the properties of Lead Alloy was evaluated. It was found that both the Lead/SiC as well as in the Lead/zircon composites, the ultimate tensile strength and hardness increased while the ductility decreased with the increase in weight % Sic and zircon in the Alloy respectively.
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Wear behaviour of Lead Alloy/zircon particulate composites
Materials & Design, 1996Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract This paper presents and analyses some results obtained in wear and hardness tests performed on a Lead-antimony Alloy dispersed with zircon particles, with and without homogenizing heat treatment. The zircon content ranged from 0% to 5% by weight and the duration of heat treatment ranged from 0 to 5 hours. It was observed that for each composite, wear increases monotonically with wear load and with wear test speed. Increasing the zircon content improves wear resistance, although this improvement diminishes as higher zircon contents are reached. Heat treatment at 200°C for up to 5 hours improves the wear resistance of the composites, although for the unreinforced Lead Alloy, the greatest benefit is achieved within the first hour of heat treatment.
Hongli Chen - One of the best experts on this subject based on the ideXlab platform.
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subchannel analysis of fuel assemblies of a Lead Alloy cooled fast reactor
Progress in Nuclear Energy, 2015Co-Authors: Hongli Chen, Guangming Zhou, Zhao Chen, Shuzhou Li, Pengcheng ZhaoAbstract:Abstract Lead–Alloy cooled fast reactor is one of the six Gen-IV reactors. It has many attractive features such as excellent natural circulation performance, better shielding against gamma rays or energetic neutrons and potentially reduced capital costs. A natural circulation Lead–Alloy cooled fast reactor with 10 MWth is under design in China (hereafter called LFR-10MW). Fuel assemblies thermal hydraulic analysis is of vital importance for a successful design. A subchannel analysis code with flow distribution model was used to carry out the thermal hydraulic analysis. This work briefly gave the thermal-hydraulic design for the LFR-10MW and analyzed the thermal-hydraulic characteristics under steady-state condition using the subchannel analysis code. Whole core analysis was performed to locate the hottest fuel assembly using the code. The hottest fuel assembly was analyzed to obtain the cladding temperature, fuel temperature and coolant velocity. The maximum cladding temperature, the maximum fuel center temperature and the maximum coolant velocity are all below the design constraints. These results imply that the thermal-hydraulic design of LFR-10MW is feasible.
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development and application of a thermal hydraulics analysis code for small modular natural circulation Lead or Lead Alloy cooled fast reactors
Annals of Nuclear Energy, 2014Co-Authors: Zhao Chen, Guangming Zhou, Pengcheng Zhao, Hongli ChenAbstract:Abstract Small modular natural circulation Lead or Lead-Alloy cooled fast reactor (LFR) is one of the potential candidates for passive cooling SMR development. In a pump-forced reactor, the coolant mass flow rate is determined by the pump power, while in a small modular natural circulation LFR, the coolant mass flow rate is determined from the balance between the driving force (due to density difference between hot and cold sides) and the resistance force (due to pressure drop in the system). For this reason, the effects of the core coolant channel geometry on the thermal-hydraulics performance in a small modular natural circulation LFR is more sensitive than that in a pump-forced reactor. This problem is not considered in existing thermal-hydraulics analysis codes, which are developed for pump-forced reactors originally. In this paper, a thermal-hydraulics analysis code for small modular natural circulation LFRs was developed, which is based on the mathematical models for natural circulation reactors originally. A validation case from Argonne National Laboratory (ANL) was chosen and calculated by using this code and the results agree fairly well with the ANL’s ones. As a typical application case, the thermal-hydraulics design and core coolant channel geometry effect analysis of a 10 MW natural circulation LFR was carried out.
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study of core flow distribution for small modular natural circulation Lead or Lead Alloy cooled fast reactors
Annals of Nuclear Energy, 2014Co-Authors: Zhao Chen, Gguangming Zhou, Pengcheng Zhao, Hongli ChenAbstract:Abstract Small modular natural circulation Lead or Lead-Alloy cooled fast reactor (LFR) is a potential candidate for LFR development. It has many attractive advantages such as reduced capital costs and inherent safety. The core flow distribution calculation is an important issue for nuclear reactor design, which will provide important input parameters to thermal-hydraulic analysis and safety analysis. The core flow distribution calculation of a natural circulation LFR is different from that of a forced circulation reactor. In a forced circulation reactor, the core flow distribution can be controlled and adjusted by the pump power and the flow distributor, while in a natural circulation reactor, the core flow distribution is automatically adjusted according to the relationship between the local power and the local resistance feature. In this paper, a non-uniform heated parallel channel flow distribution calculation code was developed and the comparison study between the channel method and the CFD method was carried out to assess the exactness of the developed code. The core flow distribution analysis and optimization design for a 10MW natural circulation LFR was conducted using the developed code. A core flow distribution optimization design scheme for a 10MW natural circulation LFR was proposed according to the optimization analysis results.
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cfd analysis of circumferential temperature distribution on fuel cladding surface of china Lead Alloy cooled research reactor clear i
Volume 3: Nuclear Safety and Security; Codes Standards Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, 2013Co-Authors: Guangming Zhou, Zhao Chen, Hongli Chen, Tao ZhouAbstract:Because of heterogeneity of sub-channels geometry, a circumferential temperature distribution will exit in the fuel cladding surface during operating condition of a nuclear reactor, which will increase the maximum cladding surface temperature (MCST). However, this phenomenon cannot be obtained in single channel or sub-channel analyses approach. Computational Fluid Dynamics (CFD) is a good method to study this problem. In this paper, the circumferential temperature distribution on the fuel cladding surface of different sub-channels of China Lead-Alloy Cooled Research Reactor (CLEAR-I) were studied using FLUENT 14.0. Obvious circumferential temperature distributions were presented in results and the maximum circumferential temperature difference is 13°C in edge-channels. This study will improve the precision in the MCST calculation of CLEAR-I and be a good guideline to the optimum design of CLEAR-I sub-channels configurations.Copyright © 2013 by ASME
K.h.w. Seah - One of the best experts on this subject based on the ideXlab platform.
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Corrosion behaviour of Lead Alloy/zircon particulate composites
Corrosion Science, 1997Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract A study of the corrosion behaviour of Lead Alloy matrix composites containing varying amounts of zircon particles shows that the corrosion resistance of the composites decreases with increase in zircon content. However, heat treatment at 200 °C for up to 5 h seems to improve the corrosion resistance. An attempt is made in the paper to explain these phenomena.
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Wear behaviour of Lead Alloy/zircon particulate composites
Materials & Design, 1996Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract This paper presents and analyses some results obtained in wear and hardness tests performed on a Lead-antimony Alloy dispersed with zircon particles, with and without homogenizing heat treatment. The zircon content ranged from 0% to 5% by weight and the duration of heat treatment ranged from 0 to 5 hours. It was observed that for each composite, wear increases monotonically with wear load and with wear test speed. Increasing the zircon content improves wear resistance, although this improvement diminishes as higher zircon contents are reached. Heat treatment at 200°C for up to 5 hours improves the wear resistance of the composites, although for the unreinforced Lead Alloy, the greatest benefit is achieved within the first hour of heat treatment.
J. Venkatesh - One of the best experts on this subject based on the ideXlab platform.
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Corrosion behaviour of Lead Alloy/zircon particulate composites
Corrosion Science, 1997Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract A study of the corrosion behaviour of Lead Alloy matrix composites containing varying amounts of zircon particles shows that the corrosion resistance of the composites decreases with increase in zircon content. However, heat treatment at 200 °C for up to 5 h seems to improve the corrosion resistance. An attempt is made in the paper to explain these phenomena.
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Mechanical properties of Lead Alloy based composite materials for battery applications
1996Co-Authors: Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:The present paper is a report of an investigation made into the mechanical properties of Lead Alloy composite materials reinforced with two different ceramic particles namely zircon and Sic. The Lead-antimony Alloy(Lead 80% and antimony 20%)was used as the base matrix Alloy in either case. The composite materials were fabricated using vortex method by dispersing the ceramic particles from 1 to 5 percent by weight in steps of 2% into the molten Lead Alloy above the liquidus temperature. The size of the part-icles used was 90 to 150 um in either case. The influence of the two dispersoids on the properties on the properties of Lead Alloy was evaluated. It was found that both the Lead/SiC as well as in the Lead/zircon composites, the ultimate tensile strength and hardness increased while the ductility decreased with the increase in weight % Sic and zircon in the Alloy respectively.
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Wear behaviour of Lead Alloy/zircon particulate composites
Materials & Design, 1996Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract This paper presents and analyses some results obtained in wear and hardness tests performed on a Lead-antimony Alloy dispersed with zircon particles, with and without homogenizing heat treatment. The zircon content ranged from 0% to 5% by weight and the duration of heat treatment ranged from 0 to 5 hours. It was observed that for each composite, wear increases monotonically with wear load and with wear test speed. Increasing the zircon content improves wear resistance, although this improvement diminishes as higher zircon contents are reached. Heat treatment at 200°C for up to 5 hours improves the wear resistance of the composites, although for the unreinforced Lead Alloy, the greatest benefit is achieved within the first hour of heat treatment.
Suresh C. Sharma - One of the best experts on this subject based on the ideXlab platform.
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Corrosion behaviour of Lead Alloy/zircon particulate composites
Corrosion Science, 1997Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract A study of the corrosion behaviour of Lead Alloy matrix composites containing varying amounts of zircon particles shows that the corrosion resistance of the composites decreases with increase in zircon content. However, heat treatment at 200 °C for up to 5 h seems to improve the corrosion resistance. An attempt is made in the paper to explain these phenomena.
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Mechanical properties of Lead Alloy based composite materials for battery applications
1996Co-Authors: Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:The present paper is a report of an investigation made into the mechanical properties of Lead Alloy composite materials reinforced with two different ceramic particles namely zircon and Sic. The Lead-antimony Alloy(Lead 80% and antimony 20%)was used as the base matrix Alloy in either case. The composite materials were fabricated using vortex method by dispersing the ceramic particles from 1 to 5 percent by weight in steps of 2% into the molten Lead Alloy above the liquidus temperature. The size of the part-icles used was 90 to 150 um in either case. The influence of the two dispersoids on the properties on the properties of Lead Alloy was evaluated. It was found that both the Lead/SiC as well as in the Lead/zircon composites, the ultimate tensile strength and hardness increased while the ductility decreased with the increase in weight % Sic and zircon in the Alloy respectively.
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Wear behaviour of Lead Alloy/zircon particulate composites
Materials & Design, 1996Co-Authors: K.h.w. Seah, Suresh C. Sharma, J. Venkatesh, B.m. GirishAbstract:Abstract This paper presents and analyses some results obtained in wear and hardness tests performed on a Lead-antimony Alloy dispersed with zircon particles, with and without homogenizing heat treatment. The zircon content ranged from 0% to 5% by weight and the duration of heat treatment ranged from 0 to 5 hours. It was observed that for each composite, wear increases monotonically with wear load and with wear test speed. Increasing the zircon content improves wear resistance, although this improvement diminishes as higher zircon contents are reached. Heat treatment at 200°C for up to 5 hours improves the wear resistance of the composites, although for the unreinforced Lead Alloy, the greatest benefit is achieved within the first hour of heat treatment.