Development of a linearized model of a pressurized water reactor generating station for power system dynamic simulations

Samet E. Arda, Keith Holbert, John Undrill

Research output: Chapter in Book/Report/Conference proceedingConference contribution

7 Scopus citations

Abstract

A pressurized water reactor (PWR) nuclear power plant (NPP) model is introduced into Positive Sequence Load Flow (PSLF) software in order to evaluate the load-following capability of NPPs. The nuclear steam supply system (NSSS) consists of a reactor core, hot and cold legs, plenums, and a U-tube steam generator. The physical systems listed above are represented by mathematical models utilizing a state variable lumped parameter approach. A steady-state control program for the reactor, and simple turbine and governor models are also developed. Subsequently, the NSSS representation is incorporated into PSLF and coupled with built-in excitation system and generator models. Different simulation cases are run when sudden loss of generation occurs in a power system which includes hydroelectric and natural gas power plants besides the developed PWR NPP. The effect of the load-following operational mode on the key variables of the NSSS is observed.

Original languageEnglish (US)
Title of host publication45th North American Power Symposium, NAPS 2013
DOIs
StatePublished - Dec 1 2013
Event45th North American Power Symposium, NAPS 2013 - Manhattan, KS, United States
Duration: Sep 22 2013Sep 24 2013

Publication series

Name45th North American Power Symposium, NAPS 2013

Other

Other45th North American Power Symposium, NAPS 2013
CountryUnited States
CityManhattan, KS
Period9/22/139/24/13

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Fuel Technology

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