Using Criticality Analysis to Identify Impact of Valve Location.
使用临界分析识别阀门位置产生的影响。
Failure mode, effect and criticality analysis (FMECA) is an effective technique to improve the reliability of products.
故障模式、影响及致命度分析(简称FMECA)是提高产品可靠性的一种有效的工具。
The analysis methods most in use have Fault Tree analysis (FTA) and Failure Model Effect and Criticality analysis (FMECA).
常用的分析方法有失效树分析(FTA)和失效模式影响及致命度分析(FMECA)。
Failure criticality analysis is an important process to the research of construction machinery's optimal design and the improvement of its reliability.
失效致命度分析是研究工程机械优化设计、提高其可靠性的重要环节。
It is shown by the instance of criticality analysis of plastic extruder that the proposed method is effective for evaluating the equipment criticality.
将其应用到塑料挤出机的重要度分析中，结果表明，该方法对设备重要度的确定是有效的和实用的。
It also makes the failure mode researches, FTA analysis and failure mode Effect and Criticality analysis (FMECA) based on practical use of the chemical power source.
结合化学电源的使用效果，完成了化学电源的故障模式研究和电池故障树(FTA)分析和故障模式影响及危害分析(FMECA)。
Failure Mode Effects and Criticality Analysis(FMECA) is a good scientific method summarized from engineering practice. It is very useful in the Criticality Analysis of medical device.
故障模式影响及危害性分析技术是从工程实践中总结的分析方法，也是目前医疗器械产品安全性分析中最基本的、应用最广泛的、收效最大的分析方法之一。
The geometric buckling is of great value in application to criticality problem and analysis of dynamic process of supercritical system in fast fission reactor.
在快裂变反应堆的临界问题和超临界系统动力学过程的分析中，几何曲率有重要的应用价值。
Many organizations were involved in the JCO criticality accident processing, accident analysis, emergency radiation monitoring, environmental and health effect evaluation and public communication.
事故发生后日本有关部门和机构对事故处理、事故分析、应急监测、事故影响评价、公众沟通等方面做了大量工作。
Taking a spent fuel shipping cask as calculated model, detailed criticality safety, nuclear heat distribution and shielding calculations and sensitivity analysis of some parameters were performed.
以某型乏燃料运输容器为计算模型，对其进行了临界安全、核热分布以及辐射屏蔽计算，并对临界计算和屏蔽计算的部分参数进行了敏感性分析。
Taking a spent fuel shipping cask as calculated model, detailed criticality safety, nuclear heat distribution and shielding calculations and sensitivity analysis of some parameters were performed.
以某型乏燃料运输容器为计算模型，对其进行了临界安全、核热分布以及辐射屏蔽计算，并对临界计算和屏蔽计算的部分参数进行了敏感性分析。
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