criticality safety

Monte Carlo Approach towards Calculation for Nuclear Criticality Safety

用蒙特卡罗方法进行核临界安全计算

First Start-Up of Nuclear Criticality Safety Experiment Facility for Uranyl Nitrate Solution

铀溶液核临界安全实验装置首次物理启动

As a result , it can be a theoretical basis in nuclear criticality safety for reality production .

计算结果为实际生产中的核临界安全性提供了理论依据。

Calculation of Nuclear Criticality Safety for Duration of Materials Handling from Container at Uranium Enrichment Plant

铀富集厂容器取料过程中的核临界安全计算

One of the most important applications of the Monte Carlo method is the calculation of the nuclear criticality safety .

核临界安全计算是蒙特卡罗方法的重要应用领域之一。

Monte-Carlo Calculation of Nuclear Criticality Safety of Uranium-Water System

铀水系统核临界安全的蒙特卡罗计算

This paper described the design mind and support technology and system principle of the control protection system of nuclear criticality safety experiment facility for nitride uranium solution .

主要阐述了铀溶液核临界安全实验装置控制保护系统的设计思想、保障技术和系统原理。

Nuclear criticality safety for fissile materials outside reactors & Safety controls in conducting subcritical neutron multiplication measurements in situ

GB15146.7-1994反应堆外易裂变材料的核临界安全次临界中子增殖就地测量安全规定

This paper gives an overview of the technology of criticality safety in the next decade , and a preliminary discussion on some concerning criticality safety problems .

本文展望了未来十年的临界安全技术，并对其中一些问题作了初步探讨。

The nuclear fissile reaction system , which provides nuclear energy or neutrons , theoretically demands its criticality safety and neutron energy spectrum to be predicated .

对于提供核能源或中子源的核裂变反应系统，需从理论上给出它的临界安全性和中子能谱，通常通过k本征值问题的计算来实现。

In general , when doing analyses of criticality safety of spent fuel transport or storage , one assumption is that the compositions of the spent fuel are same as the fresh fuel .

然后再利用上一步计算得到的乏燃料成分，对特定结构的水池进行临界安全分析。

The article presents the process of calculating the critical mass of nitride uranium solution by the reciprocal extrapolation method when doing the criticality safety experiment for different concentration of nitride uranium solution in the nitride solution nuclear criticality safety experimental facility .

介绍了在硝酸铀溶液核临界安全实验装置上进行不同浓度铀溶液的临界实验时，用倒数外推方法确定硝酸铀酰的核临界质量的过程；

By using this package , the 63-group multigroup constants working file MC is generated and interconnected with the nuclear engineering criticality safety Monte Carlo NEMCS program . By which the effective multiplication factors of Pu and U systems are calculated , the primary results are satisfied .

利用这个程序包产生了63群多群常数工作库MC，将它与核工程临界安全计算MonteCarlo程序NEMCS相联接，并计算了Pu和U系统的有效增殖因数，取得了初步满意的结果。

To generate a clear spent fuel assemblies loading criteria ( to meet the criticality criteria of the safety analyses ) for a special spent fuel pool .

最终要清晰地表示出一个特定的水池对可装入（符合临界安全标准）乏燃料组件的要求。