DocumentCode
1532355
Title
A constant reactor-outlet-temperature control system for nuclear power plants
Author
Stubbs, Gilbert S.
Author_Institution
The Franklin Institute Laboratories for Research and Development Philadelphia, Pennsylvania
Issue
1
fYear
1954
Firstpage
8
Lastpage
11
Abstract
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.
Keywords
Boilers; Coolants; FIssion reactors; Inductors; Nuclear power generation; Temperature measurement;
fLanguage
English
Journal_Title
Nuclear Science, Transactions of the Institute of Radio Engineers Professional Group on
Publisher
ieee
ISSN
0277-6278
Type
jour
DOI
10.1109/IREPGTNS.1954.6499134
Filename
6499134
Link To Document