反应性控制系统的设计是反应堆物理设计的主要内容之一。氟盐冷却高温球床堆(Pebble Bed-Fluoride salt-cooled High temperature Reactor,PB-FHR)用B4C吸收体的控制棒作为反应性控制的主要手段。所有控制棒分布于石墨反射层的孔道中,...反应性控制系统的设计是反应堆物理设计的主要内容之一。氟盐冷却高温球床堆(Pebble Bed-Fluoride salt-cooled High temperature Reactor,PB-FHR)用B4C吸收体的控制棒作为反应性控制的主要手段。所有控制棒分布于石墨反射层的孔道中,其空间布局、几何结构、中子吸收体的特性参数等是影响控制棒反应性控制的关键因素。本文基于SCALE6程序,以10 MW固态燃料钍基熔盐堆(Thorium Molten Salt Reactor-Solid Fuel,TMSR-SF1)(属于PB-FHR)设计模型为参考,系统研究了石墨反射层中控制棒径向位置、有效行程、棒体结构、吸收体长度、吸收体密度等因素对控制棒价值的影响。结果表明,控制棒的径向位置对控制棒价值影响较大;控制棒吸收体长度需综合考虑上下限位及极限下插限位对价值变化的影响;^(10)B的原子密度变化对控制棒价值影响较小。本研究为PB-FHR的反应性控制系统的设计及控制棒的制造加工提供理论参考。展开更多
For designing and optimizing the reactor core of modular pebble-bed fluoride salt-cooled high-temperature reactor(PB-FHR),it is of importance to simulate the coupled fluid and particle flow due to strong coolantpebble...For designing and optimizing the reactor core of modular pebble-bed fluoride salt-cooled high-temperature reactor(PB-FHR),it is of importance to simulate the coupled fluid and particle flow due to strong coolantpebble interactions.Computational fluid dynamics and discrete element method(DEM) coupling approach can be used to track particles individually while it requires a fluid cell being greater than the pebble diameter.However,the large size of pebbles makes the fluid grid too coarse to capture the complicated flow pattern.To solve this problem,a two-grid approach is proposed to calculate interphase momentum transfer between pebbles and coolant without the constraint on the shape and size of fluid meshes.The solid velocity,fluid velocity,fluid pressure and void fraction are mapped between hexahedral coarse particle grid and tine fluid grid.Then the total interphase force can be calculated independently to speed up computation.To evaluate suitability of this two-grid approach,the pressure drop and minimum fluidization velocity of a fluidized bed were predicted,and movements of the pebbles in complex flow field were studied experimentally and numerically.The spouting fluid through a central inlet pipe of a scaled visible PB-FHR core facility was set up to provide the complex flow field.Water was chosen as Liquid to simulate the molten salt coolant,and polypropylene balls were used to simulate the pebble fuels.Results show that the pebble flow pattern captured from experiment agrees well with the simulation from two-grid approach,hence the applicability of the two-grid approach for the later PB-FHR core design.展开更多
The fluoride salt-cooled high-temperature reactor(FHR) uses molten FLi Be salt as the coolant, which introduces a corrosive effect on the alloy-N structure material. Fission neutrons activate the corroded alloy-N,alon...The fluoride salt-cooled high-temperature reactor(FHR) uses molten FLi Be salt as the coolant, which introduces a corrosive effect on the alloy-N structure material. Fission neutrons activate the corroded alloy-N,along with alloy-N structures inside the reactor vessel. The activation products of the alloy-N have a big impact on radiation protection during operation, maintenance, and decommissioning of the reactor. We have constructed a SCALE 6.1 model for the core of a typical 10 MW th FHR and analyzed the activity of each constituent of the irradiated alloy-N. The results show that the activity is predominantly due to short-lived^(28) Al,^(60m) Co,^(56) Mn,^(51)Ti, and ^(52) V, as well as long-lived ^(60) Co,^(51)Cr,^(55)Fe,^(59)Fe, and ^(54) Mn.Furthermore, because of their relatively long half-life and high-energy c-rays emissions,^(60) Co and ^(54)Mn are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of ^(60)Co and ^(54)Mn per unit mass of alloy-N under the current core design is 5.58*10~5 and 1.55 * 10~3 Bq MWd^(-1)g^(-1), respectively.The results of this paper, combined with future corrosion studies, may provide a basis for evaluating long-term radiation source terms of the primary loop salt and components.展开更多
基于轻水堆最佳估算系统分析程序RELAP/SCDAPSIM/MOD4.0,添加新的FLi Na K熔盐热物性参数和适用于熔盐的对流换热系数,开发了适用于FHR系统的热工水力分析程序RELAP5-FHR。通过FLi Na K高温熔盐实验回路对RELAP5-FHR程序进行实验验证。...基于轻水堆最佳估算系统分析程序RELAP/SCDAPSIM/MOD4.0,添加新的FLi Na K熔盐热物性参数和适用于熔盐的对流换热系数,开发了适用于FHR系统的热工水力分析程序RELAP5-FHR。通过FLi Na K高温熔盐实验回路对RELAP5-FHR程序进行实验验证。结果表明:RELAP5-FHR程序计算值与实验值吻合较好,验证了程序的适用性。展开更多
文摘反应性控制系统的设计是反应堆物理设计的主要内容之一。氟盐冷却高温球床堆(Pebble Bed-Fluoride salt-cooled High temperature Reactor,PB-FHR)用B4C吸收体的控制棒作为反应性控制的主要手段。所有控制棒分布于石墨反射层的孔道中,其空间布局、几何结构、中子吸收体的特性参数等是影响控制棒反应性控制的关键因素。本文基于SCALE6程序,以10 MW固态燃料钍基熔盐堆(Thorium Molten Salt Reactor-Solid Fuel,TMSR-SF1)(属于PB-FHR)设计模型为参考,系统研究了石墨反射层中控制棒径向位置、有效行程、棒体结构、吸收体长度、吸收体密度等因素对控制棒价值的影响。结果表明,控制棒的径向位置对控制棒价值影响较大;控制棒吸收体长度需综合考虑上下限位及极限下插限位对价值变化的影响;^(10)B的原子密度变化对控制棒价值影响较小。本研究为PB-FHR的反应性控制系统的设计及控制棒的制造加工提供理论参考。
基金supported by the "Strategic Priority Research Program" of the Chinese Academy of Sciences(No.XD02001002)
文摘For designing and optimizing the reactor core of modular pebble-bed fluoride salt-cooled high-temperature reactor(PB-FHR),it is of importance to simulate the coupled fluid and particle flow due to strong coolantpebble interactions.Computational fluid dynamics and discrete element method(DEM) coupling approach can be used to track particles individually while it requires a fluid cell being greater than the pebble diameter.However,the large size of pebbles makes the fluid grid too coarse to capture the complicated flow pattern.To solve this problem,a two-grid approach is proposed to calculate interphase momentum transfer between pebbles and coolant without the constraint on the shape and size of fluid meshes.The solid velocity,fluid velocity,fluid pressure and void fraction are mapped between hexahedral coarse particle grid and tine fluid grid.Then the total interphase force can be calculated independently to speed up computation.To evaluate suitability of this two-grid approach,the pressure drop and minimum fluidization velocity of a fluidized bed were predicted,and movements of the pebbles in complex flow field were studied experimentally and numerically.The spouting fluid through a central inlet pipe of a scaled visible PB-FHR core facility was set up to provide the complex flow field.Water was chosen as Liquid to simulate the molten salt coolant,and polypropylene balls were used to simulate the pebble fuels.Results show that the pebble flow pattern captured from experiment agrees well with the simulation from two-grid approach,hence the applicability of the two-grid approach for the later PB-FHR core design.
基金Supported by the ‘‘Strategic Priority Research Program’’ of the Chinese Academy of Sciences(Grant No.XDA02050100)
文摘The fluoride salt-cooled high-temperature reactor(FHR) uses molten FLi Be salt as the coolant, which introduces a corrosive effect on the alloy-N structure material. Fission neutrons activate the corroded alloy-N,along with alloy-N structures inside the reactor vessel. The activation products of the alloy-N have a big impact on radiation protection during operation, maintenance, and decommissioning of the reactor. We have constructed a SCALE 6.1 model for the core of a typical 10 MW th FHR and analyzed the activity of each constituent of the irradiated alloy-N. The results show that the activity is predominantly due to short-lived^(28) Al,^(60m) Co,^(56) Mn,^(51)Ti, and ^(52) V, as well as long-lived ^(60) Co,^(51)Cr,^(55)Fe,^(59)Fe, and ^(54) Mn.Furthermore, because of their relatively long half-life and high-energy c-rays emissions,^(60) Co and ^(54)Mn are the major contributors to the radiation source terms introduced by alloy-N activation. The yield of ^(60)Co and ^(54)Mn per unit mass of alloy-N under the current core design is 5.58*10~5 and 1.55 * 10~3 Bq MWd^(-1)g^(-1), respectively.The results of this paper, combined with future corrosion studies, may provide a basis for evaluating long-term radiation source terms of the primary loop salt and components.
文摘基于轻水堆最佳估算系统分析程序RELAP/SCDAPSIM/MOD4.0,添加新的FLi Na K熔盐热物性参数和适用于熔盐的对流换热系数,开发了适用于FHR系统的热工水力分析程序RELAP5-FHR。通过FLi Na K高温熔盐实验回路对RELAP5-FHR程序进行实验验证。结果表明:RELAP5-FHR程序计算值与实验值吻合较好,验证了程序的适用性。
