thermal neutron reactor

Solving measurement flux spectra in thermal neutron reactor with flexible tolerance method

热堆内测量中子通量谱的可变容差法解

Measurement of distribution of fast and thermal neutron fluence rate around reactor with SSNTD

用固体核径迹探测器测量反应堆周围的快、热中子注量率分布

The method is very useful for the determination of a higher integral thermal neutron flux in a high flux reactor for a long period of irradiation time.

本法适于测定在高通量堆中长期辐照的较高热中子积分通量。

Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method

用钴活化法测定反应堆中热中子积分通量

A method is presented for the measurement of integrated thermal neutron flux in a high flux reactor by a Co-activation method.

本文叙述了用钴活化法测定高通量堆中热中子积分通量的方法。

The neutron energy spectrum at the thermal column of the heavy water reactor of China Institute of Atomic Energy has been measured by using a mechanical chopper by time-of-flight method. The result shows that the energy spectrum deviates from Maxwell distribution.

利用飞行时间法，用机械选择器测量了中国原子能科学研究院重水反应堆热柱的中子能谱.结果表明，该热柱能谱和理论Maxwel谱有偏离。

Based on the code, the code system for streaming calculation was constituted and was used for calculating neutron streaming through the thermal insulator annular gap of actual reactor pressure vessel.

以它为主体，建立了辐射泄漏计算程序系统，并运用该系统进行了反应堆压力容器绝热层缝中子泄漏计算研究。