核反应堆本身的建造即伴随着许多可能的“尝试”，因此科学家们准备了多种试验材料。
The reactor itself was built with a lot of “debugging” possibilities on purpose, so that scientists could have a lot of experimental material available.
加拿大早在1944年就开始了核项目，1947年它建造了第一台试验性的核反应堆。
Canada began its nuclear program as early as 1944 and built its first experimental reactor in 1947.
其它的几个核反应堆和核能火箭设计被试验，最为成功的是Phoebus和XE-Prime。
Several other reactors and rocket designs were tested, most successfully the Phoebus and XE-Prime.
此后，将需要新一代的聚变反应堆对下一阶段，即“起爆”阶段进行试验。
A new generation fusion reactor will be needed after that to prove the next step, ignition.
本文介绍了用于快速中子反应堆安全监测的压电式高频传感器的原理、结构与试验结果。
The principle and structure of high frequency piezoelectric sensor for safe observation of fast fission reactor are introduced, and the testing results are presented.
正在试验和研究中的硼中子治疗术(BNCT)，要求设计专用反应堆，以适应大规模治疗的需要。
A special medical therapy reactor (MTR) is required for boron neutron capture therapy (BNCT), which has extended progress in some therapy tests.
在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。
After having completed the model analysis of the pressurized water reactor (PWR) core barrel in an 1:10 model, the dynamic characteristics are obtained.
在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。
After having completed the model analysis of the pressurized water reactor (PWR) core barrel in anl: 10 model, the dynamic characteristics are obtained.
本文详细介绍了在秦山核电厂原理模拟器上进行的反应堆物理模拟试验。
The reactor physical simulating test on the principle simula-for of Qinshan NPP is described in detail in this paper.
在力学试验研究中，采用声发射技术对已具有疲劳裂纹的核反应堆一回路模拟压力管进行加载爆破断裂的监测。
By using the acoustic emission technique to monitor the fractures on analogous pressure pipes of the primary circuit, which has had cracks and was loaded with pressure, was investigated.
他说，负责国际试验性热核反应堆(ITER)的国际组织即将在10月24日成立。
He said an international organization responsible for the international Thermonuclear Experimental Reactor (ITER) will be set up on October 24.
因此，必须加强高通量工程试验堆安全整治，才能确保该反应堆运行安全。
So that emphasis for the safety management must be placed on HFETR in order to ensure reactors safety.
本文介绍了反应堆整体模型水力试验原理和试验结果，并对两块实心比为0.438和0.7的流量分配板的试验结果作了分析。
This paper presents test principle and test results of whole reactor model hydraulic test. The test results of two flow distribution plates with solid ratio 0.438 and 0.7 have been analysed.
本文还简单地介绍了清华大学游泳池式反应堆供热试验的情况。
The experiment on nuclear district heating with the swimming pool reactor in Qinghua Univ. is described briefly.
本文还简单地介绍了清华大学游泳池式反应堆供热试验的情况。
The experiment on nuclear district heating with the swimming pool reactor in Qinghua Univ. is described briefly.
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