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Research Papers

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

[+] Author and Article Information
A. Gad-Briggs

EGB Engineering,
28 Beaumont Avenue,
Southwell NG25 0BB, Nottinghamshire, UK;
Gas Turbine Engineering Group,
Cranfield University,
Cranfield MK43 0AL, Bedfordshire, UK
e-mail: a.a.gadbriggs@cranfield.ac.uk

P. Pilidis

Gas Turbine Engineering Group,
Cranfield University,
Cranfield MK43 0AL, Bedfordshire, UK
e-mail: p.pilidis@cranfield.ac.uk

T. Nikolaidis

Gas Turbine Engineering Group,
Cranfield University,
Cranfield MK43 0AL, Bedfordshire, UK
e-mail: t.nikolaidis@cranfield.ac.uk

Manuscript received October 29, 2017; final manuscript received May 18, 2018; published online September 10, 2018. Assoc. Editor: Guanghui Su.

ASME J of Nuclear Rad Sci 4(4), 041014 (Sep 10, 2018) (8 pages) Paper No: NERS-17-1208; doi: 10.1115/1.4040371 History: Received October 29, 2017; Revised May 18, 2018

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 prioritization 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 °C to 50 °C and core outlet temperatures (COTs) between 750 °C and 1000 °C. The ODPs have been calculated using a tool designed for this study. Based on the results, the intercooler changes the mass flow rate and compressor pressure ratio (PR). 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 have 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 NPPs specifically gas-cooled fast reactors (GFRs) and very-high-temperature reactors (VHTRs), using helium.

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References

Locatelli, G. , Mancini, M. , and Todeschini, N. , 2013, “ Generation IV Nuclear Reactors: Current Status and Future Prospects,” Energy Policy, 61, pp. 1503–1520. [CrossRef]
Bhargava, R. K. , Bianchi, M. , Pascale, A. D. , Montenegro, G. N. , and Peretto, A. , 2007, “ Gas Turbine Based Power Cycles—A State-of-the-Art Review,” Challenges of Power Engineering and Environment, Springer, Berlin.
Gad-Briggs, A. , and Pilidis, P. , 2017, “ Analyses of the Off-Design Point Performance of a High Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants,” ASME Paper No. ICONE25-67715.
Gad-Briggs, A. , Pilidis, P. , and Nikolaidis, T. , 2017, “ Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants,” ASME J. Nucl. Eng. Radiat. Sci., 3(1), p. 011021. [CrossRef]
Gad-Briggs, A. , Pilidis, P. , and Nikolaidis, T. , 2017, “ A Review of the Turbine Cooling Fraction for Very High Turbine Entry Temperature Helium Gas Turbine Cycles for Generation IV Reactor Power Plants,” ASME J. Nucl. Eng. Radiat. Sci., 3(2), p. 021007. [CrossRef]
Gad-Briggs, A. , and Pilidis, P. , 2017, “ Analyses of Off-Design Point Performances of Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants,” ASME Paper No. ICONE25-67714.
Carre, F. , Yvon, P. , Anzieu, P. , Chauvin, N. , and Malo, J.-Y. , 2010, “ Update of the French R&D Strategy on Gas-Cooled Reactors,” Nucl. Eng. Des., 240(10), pp. 2401–2408. [CrossRef]
Gad-Briggs, A. , and Pilidis, P. , 2017, “ Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants,” ASME J. Nucl. Eng. Radiat. Sci., 3(1), p. 011017. [CrossRef]
Pradeepkumar, K. N. , Tourlidakis, A. , and Pilidis, P. , 2001, “ Analysis of 115 MW, 3-Shaft, Helium Brayton Cycle Using Nuclear Heat Source,” ASME Paper No. 2001-GT-0523.
Pradeepkumar, K. N. , Tourlidakis, A. , and Pilidis, P. , 2001, “ Design and Performance Review of PBMR Closed Cycle Gas Turbine Plant in South Africa,” International Joint Power Generation Conference, New Orleans, LA, June 4–7.
Pradeepkumar, K. N. , Tourlidakis, A. , and Pilidis, P. , 2001, “ Performance Review: PBMR Closed Cycle Gas Turbine Power Plant,” Technical Committee Meeting on HTGR—Power Conversion Systems, Palo Alto, CA, Nov. 14–16, pp. 99–112. http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/32/047/32047835.pdf?r=1
Gad-Briggs, A. , Pilidis, P. , and Nikolaidis, T. , 2017, “ 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 J. Nucl. Eng. Radiat. Sci., 3(4), p. 041016. [CrossRef]
Gad-Briggs, A. , Pilidis, P. , and Nikolaidis, T. , 2017, “ Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants,” ASME J. Nucl. Eng. Radiat. Sci., 3(4), p. 041017. [CrossRef]
Kyprianidis, K. G. , 2010, “ Multi-Disciplinary Conceptual Design of Future Jet Engine Systems,” Ph.D. thesis, Cranfield University, Cranfield, UK. https://dspace.lib.cranfield.ac.uk/handle/1826/8041
Walsh, P. P. , and Fletcher, P. , 2004, Gas Turbine Performance, 2nd ed., Blackwell Publishing, Oxford, UK.
Gad-Briggs, A. , Nikolaidis, T. , and Pilidis, P. , 2017, “ Analyses of the Effect of Cycle Inlet Temperature on the Precooler and Plant Efficiency of the Simple and Intercooled Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants,” Appl. Sci., 7(4), p. 319. [CrossRef]

Figures

Grahic Jump Location
Fig. 1

Typical IC without recuperator

Grahic Jump Location
Fig. 2

Compressor map showing corrected speed lines and contours of efficiency [14]

Grahic Jump Location
Fig. 3

Turbine map compressor map showing corrected speed lines and contours of efficiency [14]

Grahic Jump Location
Fig. 4

Performance simulation tool structure for SCR

Grahic Jump Location
Fig. 5

Plant matching process

Grahic Jump Location
Fig. 6

Intercooler component map IC and ICR

Tables

Errata

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