Analyses of the load following capabilities of Brayton Helium gas turbine cycles for generation IV nuclear power plants

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dc.contributor.author Gad-Briggs, Arnold
dc.contributor.author Pilidis, Pericles
dc.contributor.author Nikolaidis, Theoklis
dc.date.accessioned 2017-06-15T08:29:25Z
dc.date.available 2017-06-15T08:29:25Z
dc.date.issued 2017-06-09
dc.identifier.citation Arnold Gad-Briggs, Pericles Pilidis and Theoklis Nikolaidis. Analyses of the load following capabilities of Brayton Helium gas turbine cycles for generation IV nuclear power plants. Journal of Nuclear Engineering and Radiation Science, 31 July 2017, Vol. 3, Iss. 4, article id 041017 en_UK
dc.identifier.issn 2332-8983
dc.identifier.uri http://dx.doi.org/10.1115/1.4036983
dc.identifier.uri http://dspace.lib.cranfield.ac.uk/handle/1826/12024
dc.description.abstract The control system for Generation IV Nuclear Power Plant (NPP) design must ensure load variation when changes to critical parameters affect grid demand, plant efficiency and component integrity. The objective of this study is to assess the load following capabilities of cycles when inventory pressure control is utilised. Cycles of interest are Simple Cycle Recuperated (SCR), Intercooled Cycle Recuperated (ICR) and Intercooled Cycle without recuperation (IC). Firstly, part power performance of the IC is compared to results of the SCR and ICR. Subsequently, the load following capabilities are assessed when the cycle inlet temperature is varied. This was carried out using a tool designed for this study. Results show that the IC takes ~2.7% longer than the ICR to reduce the power output to 50% when operating in Design Point (DP) for similar valve flows, which correlates to the volumetric increase for the IC inventory storage tank. However, the ability of the IC to match the ICR’s load following capabilities is severely hindered because the IC is most susceptible to temperature variation. Furthermore, the IC takes longer than the SCR and ICR to regulate the reactor power by a factor of 51 but this is severely reduced, when regulating NPP power output. However, the IC is the only cycle that does not compromise reactor integrity and cycle efficiency when regulating the power. The analyses intend to aid the development of cycles specifically Gas Cooled Fast Reactors (GFRs) and Very High Temperature Reactors (VHTRs), where helium is the coolant. en_UK
dc.language.iso en en_UK
dc.publisher ASME en_UK
dc.rights Attribution 4.0 International
dc.rights.uri http://creativecommons.org/licenses/by/4.0/
dc.subject Stress en_UK
dc.subject Gas turbines en_UK
dc.subject Cycles en_UK
dc.subject Helium en_UK
dc.subject Nuclear power stations en_UK
dc.subject Very high temperature reactors en_UK
dc.subject Design en_UK
dc.subject Temperature en_UK
dc.subject Control systems en_UK
dc.subject Coolants en_UK
dc.title Analyses of the load following capabilities of Brayton Helium gas turbine cycles for generation IV nuclear power plants en_UK
dc.type Article en_UK


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