Analyses of the control system strategies and methodology for part power control of the simple and intercooled recuperated 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 Nicolaidis, Theoklis
dc.date.accessioned 2017-05-17T09:13:58Z
dc.date.available 2017-05-17T09:13:58Z
dc.date.issued 2017-05-15
dc.identifier.citation Gad-Briggs AA, Pilidis PP, Nikolaidis TT. Analyses of the control system strategies and methodology for part power control of the simple and intercooled recuperated Brayton helium gas turbine cycles for generation IV nuclear power plants. ASME Journal of Nuclear Engineering and Radiation Science, Volume 3, Issue 4, paper number 041016 en_UK
dc.identifier.issn 2332-8983
dc.identifier.uri http://dx.doi.org/10.1115/1.4036737
dc.identifier.uri http://dspace.lib.cranfield.ac.uk/handle/1826/11901
dc.description.abstract An important requirement for Generation IV Nuclear Power Plant (NPP) design is the control system, which enables part power operability. The choices of control system methods must ensure variation of load without severe drawbacks on cycle performance. The objective of this study is to assess the control of the NPP under part power operations. The cycles of interest are the Simple Cycle Recuperated (SCR) and the Intercooled Cycle Recuperated (ICR). Control strategies are proposed for NPPs but the focus is on the strategies that result in part power operation using the inventory control method. Firstly, results explaining the performance and load limiting factors of the inventory control method are documented; subsequently, the transient part power performances. The load versus efficiency curves were also derived from varying the load to understand the efficiency penalties. This is carried out using a modelling and performance simulation tool designed for this study. Results show that the ICR takes ~102% longer than the SCR to reduce the load to 50% in Design Point (DP) performance conditions for similar valve flows, which correlates to the volumetric increase for the ICR inventory tank. The efficiency penalties are comparable for both cycles at 50% part power, whereby a 22% drop in cycle efficiency was observed and indicates limiting time at very low part power. The analyses intend to aid the development of cycles for Generation IV NPPs 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 The American Society of Mechanical Engineers en_UK
dc.rights Attribution 4.0 International
dc.rights.uri http://creativecommons.org/licenses/by/4.0/
dc.subject Control systems 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 Stress en_UK
dc.subject Design en_UK
dc.subject Very high temperature reactors en_UK
dc.subject Fast neutron reactors en_UK
dc.subject Flow (Dynamics) en_UK
dc.title Analyses of the control system strategies and methodology for part power control of the simple and intercooled recuperated Brayton helium gas turbine cycles for generation IV nuclear power plants en_UK
dc.type Article en_UK


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