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The PWR Protection System - Present and Future

Authors :
D. von Haebler
C. H. Meijer
Source :
IEEE Transactions on Nuclear Science. 22:784-797
Publication Year :
1975
Publisher :
Institute of Electrical and Electronics Engineers (IEEE), 1975.

Abstract

In a nuclear power generating station, the system used to protect the reactor and its containment is the plant protection sytem. The pressurized-water-reactor (PWR) protection systems encompass all electrical and mechanical devices and circuitry (from sensors to actuated device input terminals) involved in generating those signals associated with the protective function. These signals include actuation signals for the Reactor Protection System (RPS) and Engineered Safety Features System (ESFS) such as Safety Injection Actuation System, Containment Spray Actuation System, Main Steam Isolation System, Auxiliary Feedwater Actuation System, and Recirculation Actuation System. This paper deals with the present status and future development of the Plant Protection Systems utilized by Combustion Engineering, Inc. (C-E) and Kraftwerk Union (KWU) for their Pressurized Water Reactors. The latest techniques of signal processing, logic design, reactor trip and engineered safety features actuation circuitry, automatic testing, isolation and interfacing, are discussed. Current system design criteria, which as a result of the dynamic national and international licensing atmospheres influence system design philosophies, are highlighted.

Details

ISSN :
00189499
Volume :
22
Database :
OpenAIRE
Journal :
IEEE Transactions on Nuclear Science
Accession number :
edsair.doi...........a1ba6c3d42dc6a0246a98c1c4fa860d5
Full Text :
https://doi.org/10.1109/tns.1975.4327746