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600-MW_(e)high-temperature gas-cooled reactor nuclear power plant HTR-PM600 被引量:2
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作者 Zuo-Yi Zhang Yu-Jie Dong +2 位作者 Qi Shi Fu Li Hai-Tao Wang 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第8期69-76,共8页
The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor pebble-bed module(HTR-PM)demonstration project.It utilizes proven HTR-PM reac... The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor pebble-bed module(HTR-PM)demonstration project.It utilizes proven HTR-PM reactor and steam generator modules with a thermal power of 250 MW_(th)and power generation of approximately 100 MW_(e)per module.Six modules in parallel,connected to a steam turbine,form a 600-MW_(e)nuclear power plant.In addition,its system configuration in the nuclear island is identical to that of the HTR-PM in which the technical risks are minimized.Under this principle,the HTR-PM600 achieves the same level of inherent safety as the HTR-PM.The concept of a ventilated lowpressure containment(VLPC)is unchanged;however,a large circular VLPC accommodating all six reactor modules is adopted rather than the previous small-cavity-type VLPC,which contains only one module,as defined for the HTR-PM.The layout of the nuclear island and its associated systems refer to single-unit pressurized water reactor(PWR)practices.With this layout,the HTR-PM600achieves a volume size of the nuclear island that is comparable to a domestic PWR of the same power level.This will be a GenerationⅣnuclear energy technology that is economically competitive. 展开更多
关键词 high-temperature gas-cooled reactor MODULE HTR-PM600 GenerationⅣ
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Simultaneous approach for simulation of a high-temperature gas-cooled reactor 被引量:2
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作者 Yang CHEN Jiang-hong YOU Zhi-jiang SHAO Ke-xin WANG Ji-xin QIAN 《Journal of Zhejiang University-Science A(Applied Physics & Engineering)》 SCIE EI CAS CSCD 2011年第7期567-574,共8页
The simulation of a high-temperature gas-cooled reactor pebble-bed module(HTR-PM) plant is discussed.This lumped parameter model has the form of a set differential algebraic equations(DAEs) that include stiff equation... The simulation of a high-temperature gas-cooled reactor pebble-bed module(HTR-PM) plant is discussed.This lumped parameter model has the form of a set differential algebraic equations(DAEs) that include stiff equations to model point neutron kinetics.The nested approach is the most common method to solve DAE,but this approach is very expensive and time-consuming due to inner iterations.This paper deals with an alternative approach in which a simultaneous solution method is used.The DAEs are discretized over a time horizon using collocation on finite elements,and Radau collocation points are applied.The resulting nonlinear algebraic equations can be solved by existing solvers.The discrete algorithm is discussed in detail;both accuracy and stability issues are considered.Finally,the simulation results are presented to validate the efficiency and accuracy of the simultaneous approach that takes much less time than the nested one. 展开更多
关键词 Differential algebraic equations(DAEs) high-temperature gas-cooled reactor(HTR) SIMULATION Simultaneous approach
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Evaluation of thermophoretic effects on graphite dust coagulation in high-temperature gas-cooled reactors 被引量:2
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作者 Kaiyuan Wang Suyuan Yu Wei Peng 《Particuology》 SCIE EI CAS CSCD 2020年第4期45-52,共8页
In high-temperature gas-cooled reactors,graphite dust particles within the reactor core and the heat transfer equipment experience large temperature gradients.Under such conditions,thermophoresis may play an important... In high-temperature gas-cooled reactors,graphite dust particles within the reactor core and the heat transfer equipment experience large temperature gradients.Under such conditions,thermophoresis may play an important role in determining aerosol evolution.This study presents a theoretical and numerical analysis of the thermophoretic effects on aerosol coagulation within these reactors.The coagulation rates for Brownian versus thermophoretic coagulation are calculated and compared for various temperature gradients.Our results show that thermophoretic coagulation dominates over Brownian coagulation for large temperature gradients.We defined an enhancement factor to evaluate the role of thermophoretic coagulation under various reactor conditions.The enhancement factor increased dramatically with increasing temperature gradient,decreasing pressure and increasing particle diameter,but was not very sensitive to temperature change.The time evolution of the particle size distribution related to combined Brownian and thermophoretic coagulation was simulated using a log-skew-normal method of moments.The simulation results indicate that aerosol evolution can be strongly accelerated by thermophoretic coagulation under large temperature gradients. 展开更多
关键词 Graphite dust high-temperature gas-cooled reactor Thermophoretic coagulation Log-skew-normal method of moments Particle size distribution
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Research on manufacture technology of spherical fuel elements by dry-bag isostatic pressing
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作者 Zhen-Ming Lu Wen-Ke Zhang +5 位作者 Jie Zhang Xiang-Wen Zhou Kai-Hong Zhang Ma-Lin Liu Xuan-Ke Li Bing Liu 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第10期79-89,共11页
The steady development of high-temperature gas-cooled reactors(HTRs) has increased the requirements for the production cost and quality of fuel elements. Green fuel element pressing is one of the key steps to increase... The steady development of high-temperature gas-cooled reactors(HTRs) has increased the requirements for the production cost and quality of fuel elements. Green fuel element pressing is one of the key steps to increase the production capacity. This paper proposes a proprietary vacuum dry-bag isostatic pressing(DIP) apparatus. The structural change of the matrix graphite powder during the DIP process was examined by analyzing the density change of the matrix graphite spheres with pressure. The soft molding process was simulated using the finite element method. The dimensional changes in the spheres during the pressing, carbonization, and purification stages were explored. The performance of the fuel matrix produced by the DIP method was comprehensively examined. The fuel matrix met the technical requirements and its anisotropy was significantly reduced. The DIP method can significantly improve both the production efficiency and quality of fuel elements. This will play a key role in meeting the huge demand for fuel elements of HTRs and molten salt reactors. 展开更多
关键词 Dry-bag isostatic pressing high-temperature gas-cooled reactor(HTR) Spherical fuel element Finite element simulation Soft molding
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Experimental and mechanistic study of dispersed micrometer-sized particle resuspension in a square straight duct with rough walls
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作者 Qi Sun Suyuan Yu Wei Peng 《Particuology》 SCIE EI CSCD 2023年第12期101-114,共14页
The resuspension of graphite dust is an important phenomenon in the release of radioactivity and the safety of nuclear reactors during severe accidents.In this study,a visualization experimental platform is constructe... The resuspension of graphite dust is an important phenomenon in the release of radioactivity and the safety of nuclear reactors during severe accidents.In this study,a visualization experimental platform is constructed to study effects of particle size,flow velocity,and wall roughness on the resuspension characteristics of graphite particles.A statistical model of particle resuspension applicable to monolayer dispersed particles is developed based on the moment equilibrium of the particles and the flow field characteristics,as calculated by the large-eddy simulation framework.The results show that particle resuspension can be divided into short-and long-term resuspension stages.Most particle resuspension occurs during the short-term stage.With increases in flow velocity and particle diameter,the aerodynamic or adhesion force acting on the particles increases,and corresponding particle resuspension fraction increases.The influence of rough walls on particle resuspension is related to both the force on the particles and the arm ratio between the wall morphology and the particle diameter.A comparison with the experimental results demonstrates that the particle resuspension model developed in this study accurately predicts the impact of flow velocity,particle size,and wall roughness on particle resuspension. 展开更多
关键词 Particle resuspension Statistical model Moment equilibrium High temperature gas-cooled reactor(htgr)
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Graphite dust resuspension in an HTR-10 steam generator 被引量:2
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作者 Wei Peng Tianqi Zhang +1 位作者 Yanan Zhen Suyuan Yu 《Particuology》 SCIE EI CAS CSCD 2014年第6期149-157,共9页
Graphite dust has an important effect on the safety of high-temperature gas-cooled reactors(HTR).The flow field in the steam generator was studied by the computational fluid dynamics(CFD) method,with the results i... Graphite dust has an important effect on the safety of high-temperature gas-cooled reactors(HTR).The flow field in the steam generator was studied by the computational fluid dynamics(CFD) method,with the results indicating that the friction velocity in the windward and the leeward of the heat transfer tubes is relatively low and is higher at the sides.Further analysis of the resuspension of graphite dust indicates that the resuspension fraction reaches nearly zero for particles with a diameter less than 1 μm,whereas it will increases as the helium velocity in the steam generator increases for particle size larger than 1 μm.Moreover,the resuspension fraction increases as the particle size increases.The results also indicate that resuspension of the particles with sizes larger than 1 μm exhibited obvious differences in different parts of the steam generator. 展开更多
关键词 Graphite dust high-temperature gas-cooled reactor(HTR) Steam generator RESUSPENSION
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Oxidation Behaviour of the Matrix Materials in Spherical Fuel Elements
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作者 张世超 贺俊 +1 位作者 邱学良 马昌文 《Tsinghua Science and Technology》 SCIE EI CAS 1996年第1期50-55,共6页
The oxidation resistance of the matrix materials is vital to the normal operation of HTGR and is also an important parameter for evaluating the safety response under accidental air or water ingress conditions. The oxi... The oxidation resistance of the matrix materials is vital to the normal operation of HTGR and is also an important parameter for evaluating the safety response under accidental air or water ingress conditions. The oxidation kinetics of the three matrix material components: natural graphite, artificial graphite and resin carbon. was studied in a flowing gas mixture of oxygen and nitrogen using an auto thermogravimetric system. The results indicate that the artificial graphite has the slowest oxidation rate followed by the natural graphite and then the resin carbon with the highest oxidation rate. Vacuum heat treatment of the natural graphite at 1950℃ decreases the impurities and increases the oxidation activation energy. Differences between the activation energy and the oxidation rate of the resin carbon heat treated at 1950℃ and 1600℃ resulted from changes in the micro-pore texture. and the reduction of impurities. 展开更多
关键词 OXIDATION matrix materials fuel element GRAPHITE high temperature gas-cooled reactor (htgr)
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