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提高堆芯
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  increasing core
     The DRM has been used for justifi-cation of increasing core power factor in Daya Bay NPS18-month fuel cycle project.
     该方法已在大亚湾核电站18个月换料项目的提高堆芯功率因子的分析论证中应用。
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  “提高堆芯”译为未确定词的双语例句
     This article explains this phenomenon and analyses its physical mechanism and effects of relevant parameters. Finally, it is noted that the oscillation could be avoided if negative temperature coefficient of moderator or core outlet subcooling is increased, or cross-section area of the riser is reduced.
     本文针对这一现象,分析了物理机制及参数影响,指出通过加大慢化剂负温度系数,或提高堆芯出口过冷度,或减小烟囱面积,可避免出现这种振荡。
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  相似匹配句对
     Increase cure rate.
     提高治愈率。
短句来源
     improve the staff's qualities;
     提高人员素质;
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
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  increasing core
All properties studied were positively affected by increasing core layer resin content.
      
At the four stations studied, the heterotrophic anaerobic bacteria disappeared most rapidly with increasing core depth, and the heterotrophic aerobic bacteria paradoxically seemed to be more resistant to burying conditions.
      
The down-core variation of magnetic properties suggests that the KODOS sediments were subjected to dissolution processes resulting in a loss of the more stable components of the magnetic fraction with increasing core depth.
      
During the period of increasing core temperatures NMBF was significantly correlated to Tty (r = 0.93, P = 0.0001) and Tes (r = 0.97, P = 0.0001), suggesting the blood flow change in this tissue was a thermo-regulatory response.
      
Different vascular responses in glabrous and nonglabrous skin with increasing core temperature during exercise
      
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The influence of baffle on core neutron economics is investigated and theoretic prediction has been verified through experiments conducted at a zero power reactor with baffles of various thicknesses. Although stainless steel is usuall considered as a parasitic neutron absorber, some beneficial result of baffle on core neutron economics is discovered. Since the fast neutron is reflectedy by stainless steel baffle of various thicknesses, the baffle thickness increases from 2.5 cm (this is a typical thickness of...

The influence of baffle on core neutron economics is investigated and theoretic prediction has been verified through experiments conducted at a zero power reactor with baffles of various thicknesses. Although stainless steel is usuall considered as a parasitic neutron absorber, some beneficial result of baffle on core neutron economics is discovered. Since the fast neutron is reflectedy by stainless steel baffle of various thicknesses, the baffle thickness increases from 2.5 cm (this is a typical thickness of baffle used in PWR) to 20 cm (the 20era baffle will be changed into reflector assembly of stainless steel in he construction design), then the fuel burnup lifetime for the first cycle in a 300 MWe PWR will prolong 40 EFPD. When the first cycle lifetime is converted into the equilibrium cycle lifetime (360 EFPD), a burnup lifetime gains for the stainless steel reflector of 20 cm is 33 EFPD. During 40 years (0.8 loadfactor)plant design lifetime, it may give out 7600 GMW extra power production. If the stainless steel reflector is replaced by Zr-4, the economie benefits will be much larger

本文研究了围板对堆芯中子经济的影响,并且经过不同厚度围板的零功率反应堆的实验,验证了理论予计的结果。尽管不锈钢通常被认为是一种寄生性中子吸收体,但发现围板增加到某一厚度时,反而提高了堆芯的中子经济效益。由于不同厚度不锈钢板反射中子的作用不同,当围板厚度由2.5cm(这是核电厂压水堆使用的一种代表性围板的厚度)增加到20cm(在结构设计中应将20cm的围板改变为不锈钢反射层组件)时,则30万kW的核电厂压水堆第一燃料循环的寿期将会延长40EF-PD。若把第一循环寿期转换为平衡燃料循环寿期(360EFPD),20cm不锈钢反射层则可多发33EFPD。再按40年的核电厂设计寿命(年负荷因子为0.8)折算,则可多发76亿度的电。如果不锈钢反射层用锆合金代替,其经济效益更大。

Under the loss of heat sinks ATWS (anticipated transients without scram) accident of the PWR operation of nuclear heating reactors with natural circulation, the reactor is probably to enter a low quality two-phase flow density wave instability region and an oscillation of the power and flow rate can be induced because the decrease of core power lags behind the flow rate. This article explains this phenomenon and analyses its physical mechanism and effects of relevant parameters. Finally* it is noted that the...

Under the loss of heat sinks ATWS (anticipated transients without scram) accident of the PWR operation of nuclear heating reactors with natural circulation, the reactor is probably to enter a low quality two-phase flow density wave instability region and an oscillation of the power and flow rate can be induced because the decrease of core power lags behind the flow rate. This article explains this phenomenon and analyses its physical mechanism and effects of relevant parameters. Finally* it is noted that the oscillation could be avoided if negative temperature coefficient of moderator or core outlet subcooling is increased?or cross-section area of the riser is reduced.

对于自然循环低温核供热堆的压水运行工况,在发生丧失全部热阱ATWS事故时,由于功率下降滞后于流量下降,反应堆在事故过程中可能进入低干度两相流不稳定区,堆功率及流量出现较大幅度的振动。本文针对这一现象,分析了物理机制及参数影响,指出通过加大慢化剂负温度系数、或提高堆芯出口过冷度、或减小烟囱面积,可避免出现这种振荡。

Under the loss of heat sinks AWS (anticipated transients without scram) accident of the PWR operation of nuclear heating reactors with natural circulation, the reactor is probably to enter a low quality two-phase flow density wave instability region and an oscillation of the power and flow rate can be induced because the decrease of core power lags behind the flow rate. This article explains this phenomenon and analyses its physical mechanism and effects of relevant parameters. Finally, it is noted that the...

Under the loss of heat sinks AWS (anticipated transients without scram) accident of the PWR operation of nuclear heating reactors with natural circulation, the reactor is probably to enter a low quality two-phase flow density wave instability region and an oscillation of the power and flow rate can be induced because the decrease of core power lags behind the flow rate. This article explains this phenomenon and analyses its physical mechanism and effects of relevant parameters. Finally, it is noted that the oscillation could be avoided if negative temperature coefficient of moderator or core outlet subcooling is increased, or cross-section area of the riser is reduced.

对于自然循环低温核供热堆的压水运行工况,在发生丧失全部热阱ATWS事故时,由于功率下降滞后于流量下降,反应堆在事故过程中可能进入低干度两相流不稳定区,堆功率及流量出现较大幅度的振动。本文针对这一现象,分析了物理机制及参数影响,指出通过加大慢化剂负温度系数,或提高堆芯出口过冷度,或减小烟囱面积,可避免出现这种振荡。

 
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