Analyses of long term off-design performance strategy and operation of a high pressure ratio intercooled Brayton helium gas turbine cycle for generation IV nuclear power plants

Show simple item record

dc.contributor.author Gad-Briggs, Arnold
dc.contributor.author Pilidis, Pericles
dc.contributor.author Nikolaidis, Theoklis
dc.date.accessioned 2018-08-06T14:42:09Z
dc.date.available 2018-08-06T14:42:09Z
dc.date.issued 2018-05-23
dc.identifier.citation Arnold Gad-Briggs, Pericles Pilidis and Theoklis Nikolaidis. Analyses of long term off-design performance strategy and operation of a high pressure ratio intercooled Brayton helium gas turbine cycle for generation IV nuclear power plants. Journal of Nuclear Engineering and Radiation Science, Volume 4, Issue, 4, September 2018, Article number 041014 en_UK
dc.identifier.issn 2332-8983
dc.identifier.uri https//doi.org/10.1016/j.ijplas.2018.07.009
dc.identifier.uri https://dspace.lib.cranfield.ac.uk/handle/1826/13383
dc.description.abstract The Intercooled Cycle (IC) is a simplified novel proposal for Generation IV Nuclear Power Plants (NPP) based on studies demonstrating efficiencies of over 45%. As an alternative to the Simple Cycle Recuperated (SCR) and the Intercooled Cycle Recuperated (ICR), the main difference in configuration is no recuperator, which reduces its size. It is expected that the components of the IC will not operate at optimum part power due to seasonal changes in ambient temperature and grid prioritisation for renewable sources. Thus the ability to demonstrate viable part load performance becomes an important requirement. The main objective of this study is to derive Off-Design Points (ODPs) for a temperature range of -35 to 50°C and COTs between 750 to 1000°C. The ODPs have been calculated using a tool designed for this study. Based on results, the intercooler changes the mass flow rate and compressor pressure ratio. However, a drop of ~9% in plant efficiency, in comparison to the ICR (6%) was observed for pressure losses of up to 5% . The reactor pressure losses for IC has the lowest effect on plant cycle efficiency in comparison to the SCR and ICR. Characteristic maps are created to support first order calculations. It is also proposed to consider the intercooler pressure loss as a handle for ODP performance. The analyses brings attention to the IC an alternative cycle and aids development of cycles for Generation IV Nuclear Power Plants specifically Gas Cooled Fast Reactors (GFRs) and Very High Temperature Reactors (VHTRs). en_UK
dc.language.iso en en_UK
dc.publisher ASME en_UK
dc.rights Attribution-NonCommercial 4.0 International *
dc.rights.uri http://creativecommons.org/licenses/by/4.0/ *
dc.subject circular supply chain en_UK
dc.subject circular economy en_UK
dc.subject sustainability perspectives of supply chains en_UK
dc.subject restorative processes en_UK
dc.title Analyses of long term off-design performance strategy and operation of a high pressure ratio intercooled Brayton helium gas turbine cycle for generation IV nuclear power plants en_UK
dc.type Article en_UK


Files in this item

The following license files are associated with this item:

This item appears in the following Collection(s)

Show simple item record

Attribution-NonCommercial 4.0 International Except where otherwise noted, this item's license is described as Attribution-NonCommercial 4.0 International

Search CERES


Browse

My Account

Statistics