GAS-PASS/H: A simulation code for gas reactor plant systems

U. Mertyurek, R. B. Vilim, J. E. Cahalan

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

6 Scopus citations

Abstract

A simulation code has been developed for use in safety analysis and control studies of Generation-TV gas reactor concepts. Computational efficiency is achieved by use of spatially lumped conservation equations for modeling system components. Modularized programming of these components provides the capability to configure a plant system through the user input and permits modeling of both direct and indirect cycles. Performance curves are used for modeling turbomachinery while point kinetic equations are employed for the neutronics modeling. An unprotected loss of load transient is simulated for a direct cycle gas cooled fast reactor and plant response is described.

Original languageEnglish
Title of host publicationProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Pages445-450
Number of pages6
StatePublished - 2004
Externally publishedYes
EventProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 - Pittsburgh, PA, United States
Duration: Jun 13 2004Jun 17 2004

Publication series

NameProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Conference

ConferenceProceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Country/TerritoryUnited States
CityPittsburgh, PA
Period06/13/0406/17/04

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