反应堆芯

Fuel assemblies of fast breeder reactor core submerged in the liquid sodium may vibrate under the earthquake, which possibly leads to structural damage of fuel assembly or structural deformation of the core and affects structural integrity and safety qualification of the core.

浸没在液态钠中的快堆堆芯组件在地震作用下发生振动，可能导致组件结构损坏或堆芯结构变形，从而影响反应堆结构完整性和安全。

This thesis research the structure character of nuclear core and new direct current stream generator which has internal screw and double tubes in the integral nuclear power equipment.

本文主要根据一体化核动力装置一回路中的反应堆堆芯以及具有内螺旋双层套管的新型直流蒸汽发生器这两个设备的结构特点。

In this paper, the thermal-hydraulic behaviors in the reactor core in hospital neutron irradiator is investigated .

本文对医院中子照射器的反应堆堆芯结构进行了热工水力计算分析。

The established computational method is used in hospital neutron irradiator for different power levels. The detailed fluid velocity and temperature fields in the core and the temperature of the fuel elements are calculated. The maximum power for the onset of the boiling is also predicted.

采用了确定的计算方法对反应堆实际条件下的工况进行了研究，得到了详尽的计算结果，给出了医院中子照射器堆芯的流场和温场，以及燃料元件包壳外表面和内部芯块的温度分布。

Neutron flux distributions in the reactor core are measured.

6 y( j3 w9 d) g 测量了反应堆堆芯里的中子通量分布。

The system is designed for transferring heat from the reactor core.

此系统要设计成能传输出从反应堆堆芯产生的热量。

The paper presents the nuclear design criterion,reactor core characteristics and main parameters,and shows some computer codes,calculation results and analyses.

本文介绍了CPWR640反应堆的核设计准则、堆芯特性与主要参数，并给出了堆芯核设计的主要计算机程序、计算结果及分析。

The benchmark problem for GT MHR plutonium burner accidents is a part of the IAEA Coordinated Research Program on "heat transport and afterheat removal for GCR under accident conditions" The reactor performance and RCCS capability during normal operation and two loss of forced convection accidents are analyzed using THERMIX code Results shows that the core fuel temperature and the vessel temperature below the safety limits,and the RCCS can remove the residual heat from the core after the accid...

气体透平氦气模块堆标准题是国际原子能机构关于&高温气冷堆在事故工况下的热传输和余热载出&问题的合作研究计划的一部分。本文用THERMIX程序计算了稳态和两类丧失强迫冷却事故瞬态的反应堆温度分布以及空腔冷却系统的载热能力。计算结果表明，稳态及事故中燃料和压力容器的最高温度不超过安全限值，RCCS能够有效带出堆芯余热，保证反应堆安全

All of the structural materials in the active core zone, including the CEA guide tubes and the spacer grids, are Zircaloy, which minimizes the enriched uranium requirements of the core.

在反应堆芯区，包括控制元件组件管和定位栅格架，等所有材料是锆合金材料。锆合金可以极小化堆芯区中富铀的需求。

The hot gas duct of China 500 MW Pilot High-Temperature Gas-cooled Reactor connects the reactor pressure vessel and the steam generator. The hot gas duct is the main passage of the helium from the reactor core to the steam generator.

500 MW高温气冷堆示范电站的反应堆压力容器与蒸汽发生器通过热气导管连接，热气导管是反应堆堆芯出口氦气导入蒸汽发生器的主要通道。

We have no common name for a mime of Sophron or Xenarchus and a Socratic Conversation; and we should still be without one even if the imitation in the two instances were in trimeters or elegiacs or some other kind of verse--though it is the way with people to tack on 'poet' to the name of a metre, and talk of elegiac-poets and epic-poets, thinking that they call them poets not by reason of the imitative nature of their work, but indiscriminately by reason of the metre they write in.

索夫农 、森那库斯和苏格拉底式的对话采用的模仿没有一个公共的名称；三音步诗、挽歌体或其他类型的诗的模仿也没有——人们把&诗人&这一名词和格律名称结合到一起，称之为挽歌体诗人或者史诗诗人，他们被称为诗人，似乎只是因为遵守格律写作，而非他们作品的模仿本质。

The relationship between communicative competence and grammar teaching should be that of the ends and the means.

交际能力和语法的关系应该是目标与途径的关系。