1) Fast neutron fluence
快中子注量
2) Neutron Flux
中子注量
1.
Nuclear Track Method to Measure Neutron Flux;
固体核径迹法测量中子注量研究
2.
An associated particle method to measure the neutron flux from the ~2H(d,n)~3He reaction;
~2H(d,n)~3He核反应中子注量的伴随粒子法测量
3.
Measurement of neutron flux in CFBR-Ⅱ reactor;
CFBR-Ⅱ堆中子注量测量
3) neutron fluence
中子注量
1.
The neutron fluence spectra are calculated with the TARGET code.
利用TARGET程序计算了中子注量谱,利用自行设计的反复充气式反冲质子正比计数器绝对测量了上述能量点的中子注量,合成标准不确定度≤2。
2.
The absolute neutron fluence can be determined by the 238U(n,f) cross-section and the number of the fission fragments.
利用238U裂变反应,通过测量裂变碎块的数量,能够较为准确地测量快中子注量。
3.
Aluminium and gold foils were used for neutron fluence measurements of both high-energy and ther- mal neutrons.
描述了1种联合使用活化探测器和成像盘技术(IP)探测中子注量的方法。
5) neutron flux density
中子注量率
1.
) The thermal neutron flux density distribution of the shield equipment adopting polyethylene as the moderator material was experimentally measured,and the optimum position of the neutron source and the detector was determined.
实验测定了以聚乙烯为慢化材料的中子活化分析系统的热中子注量率随源到引出孔之间的距离以及探测器处于不同位置时的分布关系,为下一步进行中子活化在线分析研究提供了依据。
2.
The time-resolved neutron flux density measurement system on HT-7 Tokamak is presented in the paper.
本文介绍了HT 7超导托卡马克上的时间分辨中子注量率测量系统。
6) neutron flux
中子注量率
1.
Study on the method of determining the sub-criticality of a reactor via the measurement of core neutron flux spatial distribution;
由中子注量率空间分布形状测量确定反应堆次临界度的方法研究
2.
Research on methods for distribution of neutron flux in the experiment target;
靶件内中子注量率分布计算方法研究
3.
Furthermore, a sort of constant neutron flux density control law is presented using a predictive control algorithm.
利用核电站反应堆中子动力学系统的单位阶跃响应数据,获得了该系统的非参数模型,且提出了一种中子注量率恒值问题的预测控制方法。
补充资料：快堆(见快中子增殖堆)
快堆(见快中子增殖堆)
fast-breeder reactor
l快堆堆。(fast一breeder reaetor)见快中子增殖
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条