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The method of verification onset of nuclear boiling in nuclear reactor channels

机译:核反应堆通道核沸腾发生的验证方法

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摘要

As it is known the essence of the problem consists of that up-to-date NPP monitoring-and-control systems being the part of NPP computer-aided manufacturing control systems (CAMCS) have in their base a deterministic approach to logistic analysis of equipment operating conditions to prevent controlled by them parameters from the falling outside preliminary set safe limits. It is obviously not enough for reliable prevention of damages that could occur in a main equipment of NPU. In a proposed study the creation of an expert system on the base of an intellectual, i.e.got by methods of artificial intellect, software efficient to solve in principal the problem of the recognition of random process, which must be identified in operating reactor equipment diagnosing, is foreseen.
机译:众所周知,问题的实质在于,作为NPP计算机辅助制造控制系统(CAMCS)的一部分的最新NPP监视和控制系统在其基础上具有确定性的方法来对设备进行物流分析防止其控制的参数超出初始设定的安全极限的运行条件。显然,这还不足以可靠地防止NPU主机中可能发生的损坏。在一项拟议的研究中,建立了基于知识分子的专家系统,该知识系统是通过人工智力方法有效地解决了随机过程识别问题的软件,该软件必须在运行反应堆设备诊断中加以识别,可以预见的。

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