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堆芯安全性
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  core safety
     These results show that the core safety isn't variation,and the fast neutron flux at the pressure vessel will be decreased greatly after replacemeat of the aluinum rod by the stainless steel rod as the outermost reflector of the core for HFETR.
     结果表明,用不锈钢代替铝棒作最外层反射层,堆芯安全性能不变,压力容器处快中子注量率被大幅度降低。
短句来源
     The linear power density margin and DNBR margin for both categories, which reflect core safety, are analyzed form the point view of reactor physics and T/H, and thus category I operating domain and category II protection set point are verified.
     从反应堆物理和热工水力学的角度论证反映一、二类工况堆芯安全性的线功率密度裕量和偏离泡核沸腾比(DNBR)裕量,从而验证一类工况反应堆运行区域和二类工况超温、超功率保护限值。
短句来源
     in this paper. The possible power distributions during the stretch out in condition I and condition II are simulated with several neutronic codes. The linear power density and DNBR margins in condition I and condition II,which reflects the core safety,have been justified.
     利用中子学计算程序对岭澳核电站延伸运行I类工况和II类工况下可能的堆芯功率分布进行了模拟,论证了I、II类工况下反映堆芯安全性的线功率密度裕度和偏离泡核沸腾比(DNBR)裕度。
短句来源
  相似匹配句对
     Security
     安全性
短句来源
     Security of computer network
     计算机网络的安全性
短句来源
     PLASMA BURNING AND CONTROL IN REACTOR CORE
     堆芯等离子体燃烧和控制
短句来源
     Core Design for AC-600
     AC—600堆芯设计
短句来源
     STUDY OF PLASMA BURNING AND CONTROL IN REACTOR
     堆芯等离子体燃烧和控制
短句来源
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  core safety
Further detailed analysis should be performed to ensure the FFF core safety also under accident conditions.
      
People are assured when there are core safety functions, less crime and a police service that meets communities' expectations to lead safe lives.
      
The EU has adopted EN60950 as the core safety standard for telecommunications equipment.
      
The intent of the audit was to only assess the Core Safety and Efficacy trials.
      
The safety of tadalafil is continually monitored worldwide to add to this core safety database.
      


The attenuation of the fast neutron flux at the pressure vessel has been estimated through the method of the fast neutron removing cross section.The gamma_induced internal heating in the stainless steel rod has been computed by DOT3.5 Code.The wall temperature and centre tenperature has been computed under the design status and current operating status of High Flux Engineering Test Reactor (HFETR),The safety evaluation of the lattice sheet and the analysis of the core preformance have been done.These results...

The attenuation of the fast neutron flux at the pressure vessel has been estimated through the method of the fast neutron removing cross section.The gamma_induced internal heating in the stainless steel rod has been computed by DOT3.5 Code.The wall temperature and centre tenperature has been computed under the design status and current operating status of High Flux Engineering Test Reactor (HFETR),The safety evaluation of the lattice sheet and the analysis of the core preformance have been done.These results show that the core safety isn't variation,and the fast neutron flux at the pressure vessel will be decreased greatly after replacemeat of the aluinum rod by the stainless steel rod as the outermost reflector of the core for HFETR.

用快中子分出截面法估算了不锈钢棒对压力容器处快中子注量率的减弱程度,用二维多群粒子输运程序DOT3.5计算了不锈钢棒的γ释热,计算了高通量工程试验堆(HFETR)设计工况和目前运行工况下不锈钢壁面温度和中心温度,对承重栅板的安全性进行了讨论,分析了不锈钢棒对堆芯的性能影响。结果表明,用不锈钢代替铝棒作最外层反射层,堆芯安全性能不变,压力容器处快中子注量率被大幅度降低。

The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced. The radial and axial power distributions of normal operation (category I or condition I) and abnormal operation (category II or condition II) are simulated by using neutronics calculation code. The linear power density margin and DNBR margin for both categories, which reflect core safety, are analyzed form the point view of reactor physics and T/H, and thus category I operating...

The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced. The radial and axial power distributions of normal operation (category I or condition I) and abnormal operation (category II or condition II) are simulated by using neutronics calculation code. The linear power density margin and DNBR margin for both categories, which reflect core safety, are analyzed form the point view of reactor physics and T/H, and thus category I operating domain and category II protection set point are verified. Besides, The verification results of reference NPP are also given.

介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。利用中子学计算程序对换料堆芯正常运行工况(一类工况或工况I)和中等频率事故工况(二类工况或工况II)中可能的堆芯功率分布进行模拟。从反应堆物理和热工水力学的角度论证反映一、二类工况堆芯安全性的线功率密度裕量和偏离泡核沸腾比(DNBR)裕量,从而验证一类工况反应堆运行区域和二类工况超温、超功率保护限值。本文还给出了大亚湾核电站18个月换料堆芯功率能力验证分析的结果。

Reloading error took place at Dampierre nuclear power Station unit 4 in April 2001 in French,which lowered the sub-critical margin.Although “the snake” reloading process is adopted in nuclear power Station in Guangdong Province,it is still necessary to perform the safety analysis focused on the similar accident during the fuel reloading,in order to verify the safety of fuel reloading process in nuclear power Station in Guangdong province.Based on the conservative calculation considering the disadvantageous fuel...

Reloading error took place at Dampierre nuclear power Station unit 4 in April 2001 in French,which lowered the sub-critical margin.Although “the snake” reloading process is adopted in nuclear power Station in Guangdong Province,it is still necessary to perform the safety analysis focused on the similar accident during the fuel reloading,in order to verify the safety of fuel reloading process in nuclear power Station in Guangdong province.Based on the conservative calculation considering the disadvantageous fuel cycle of Ling’ao and Daya Bay reactors,the results show that the similar reloading error will result in the arrangement of new fuel assemblies in one place,but the sub-criticality required by FSAR can be satisfied and safety can be guaranted.

2001年4月,法国Dampierre4机组发生了燃料装载错误,导致次临界度降低。虽然广东核电机组一直采用“蛇形”装料方式,仍然需要对其发生类似装料错误后的次临界度进行计算,分析其堆芯的安全性,以验证广东核电机组装料过程的安全保障。本文通过对不利循环的保守计算分析表明,如果岭澳核电站和大亚湾核电站发生与法国Dampierre4机组同样装载错误,虽然会造成一定程度的新燃料集中摆放,但仍能满足FSAR要求的次临界度,可以保证不发生超临界的安全事故。

 
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