0
research-article

Performance Simulation To Understand The Effects Of Multi-Fluid Scaling Of Gas Turbine Components For Generation Iv Nuclear Power Plants

[+] Author and Article Information
Emmanuel Osigwe

Power Propulsion Engineering Center, Cranfield University, Bedford, Bedfordshire, MK43 0AL, UK
Emmanuel.Osigwe@rolls-royce.com

Arnold Gad-Briggs

EGB Engineering UK, Southwell, United Kingdom, Cranfield University, Bedford, Bedfordshire, MK43 0AL, UK
a.a.gadbriggs@cranfield.ac.uk

Theoklis Nikolaidis

Power Propulsion Engineering Center, Cranfield University, Bedford, Bedfordshire, MK43 0AL, UK
t.nikolaidis@cranfield.ac.uk

Pericles Pilidis

Power Propulsion Engineering Center, Cranfield University, Bedford, Bedfordshire, MK43 0AL, UK
p.pilidis@cranfield.ac.uk

Suresh Sampath

Power Propulsion Engineering Center, Cranfield University, Bedford, Bedfordshire, MK43 0AL, UK
s.sampath@cranfield.ac.uk

1Corresponding author.

ASME doi:10.1115/1.4044406 History: Received February 13, 2019; Revised July 18, 2019

Abstract

A significant hurdle in the development of performance simulation tools to analyse and evaluate nuclear power plants (NPP) is finding data relating to component performance maps. As a result, Engineers often rely on an estimation approach using various scaling techniques. The purpose of this study is to determine the component characteristics of a closed-cycle gas turbine NPP using existing component maps with corresponding design data. The design data is applied for different working fluids using a multi-fluid scaling approach to adapt data from one component map into another. The multi-fluid scaling technique described herein was developed as an in-house computer simulation tool. This approach makes it easy to theoretically scale existing maps using similar or different working fluids without carrying out a full experimental test or repeating the whole design and development process. The results of selected case studies show a reasonable agreement with available data. 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).

Copyright (c) 2019 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In