核电站反应堆出口温度恒定控制系统

Transactions of the Institute of Radio Engineers Professional Group on Nuclear Science Pub Date : 1900-01-01 DOI:10.1109/IREPGTNS.1954.6499134

G. S. Stubbs

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引用次数: 1

摘要

大多数核电站的设计都涉及到通过气体或液体冷却剂将热量从核反应堆的核心传递到蒸汽厂的锅炉。电厂控制系统的主要功能是控制冷却剂的温度，以在锅炉和反应堆中提供所需的传热速率和温度水平。控制系统还必须防止冷却剂温度的瞬态异常，以免超过电厂的材料和结构限制。控制冷却剂温度瞬态漂移的主要障碍是:(1)这些温度变化在封闭的冷却剂循环中再循环的趋势，(2)与冷却剂循环相关的长传输滞后，以及(3)测量冷却剂温度的温度计固有的大时间滞后。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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A constant reactor-outlet-temperature control system for nuclear power plants

Most nuclear power plant designs involve the transmission of heat from the core of a nuclear reactor to the boiler of a steam plant by a gas or liquid coolant. A primary function of the power plant control system is to control the temperature of this coolant to provide the desired heat transfer rates and temperature levels in the boiler and reactor. The control system must also prevent transient excusions in the coolant temperature from exceeding the material and structural limitations of the power plant. Major obstacles to the control of transient excursions in coolant temperature are (1) the tendency of these temperature variations to be recirculated in the closed coolant loop, (2) the long transport lags associated with the coolant circulation, and (3) the large inherent time lags of thermometers measuring the coolant temperature.

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Transactions of the Institute of Radio Engineers Professional Group on Nuclear Science

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