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 utilized. Cycles of interest are simple cycle recuperated (SCR), intercooled cycle recuperated (ICR), and intercooled cycle without recuperation (IC). First, 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 temperatures are 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.

References

References
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.
, epub.
2.
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
.
3.
Locatelli
,
G.
,
Mancini
,
M.
, and
Todeschini
,
N.
,
2013
, “
Generation IV Nuclear Reactors: Current Status and Future Prospects
,”
Energy Policy
,
61
, pp.
1503
1520
.
4.
Kulhanek
,
M.
, and
Dostal
,
V.
,
2007
, “
Supercritical Carbon Dioxide Cycles. Thermodynamic Analysis and Comparison
,” Czech Technical University in Prague, Prague, Czech Republic.
5.
Baxi
,
C. B.
,
Shenoy
,
A.
,
Kostin
,
V. I.
,
Kodochigov
,
N. G.
,
Vasyaev
,
A. V.
,
Belov
,
S. E.
, and
Golovko
,
V. F.
,
2008
, “
Evaluation of Alternate Power Conversion Unit Designs for the GT-MHR
,”
Nucl. Eng. Des.
,
238
(
11
), pp.
2995
3001
.
6.
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.
7.
Pradeepkumar
,
K. N.
,
Tourlidakis
,
A.
, and
Pilidis
,
P.
,
2001
, “
Analysis of a 115MW, 3-Shaft, Helium Brayton Cycle Using Nuclear Heat Source
,”
ASME
Paper No. 2001-GT-0523.
8.
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
, San Antonio, TX, June 4–7, pp. 99–112.
9.
Pradeepkumar
,
K. N.
,
Tourlidakis
,
A.
, and
Pilidis
,
P.
,
2001
, “
Performance Review: PBMR Closed Cycle Gas Turbine Power Plant
,”
Technical Committee Meeting on Gas Turbine Power Conversion Systems for Modular HTGRs
, Palo Alto, CA, Nov. 14–16, pp.
99
112
.https://inis.iaea.org/search/search.aspx?orig_q=RN:32047835
10.
Bammert
,
K.
, and
Krey
,
G.
,
1971
, “
Dynamic Behaviour and Control of Single-Shaft Closed-Cycle Gas Turbines
,”
ASME J. Eng. Power
,
93
(
4
), pp.
447
453
.
11.
Sato
,
H.
,
Yan
,
X. L.
,
Tachibana
,
Y.
, and
Kunitomi
,
K.
,
2014
, “
GTHTR300—A Nuclear Power Plant Design With 50% Generating Efficiency
,”
Nucl. Eng. Des.
,
275
, pp.
190
196
.
12.
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
.
13.
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
.
14.
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
,”
25th International Conference on Nuclear Engineering
(ICONE25), Shanghai, China, July 2–6, Paper No. ICONE25-67714.
15.
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
,”
25th International Conference on Nuclear Engineering
(ICONE25), Shanghai, China, July 2–6, Paper No. ICONE25-67715.
16.
Sato
,
H.
,
Yan
,
X. L.
,
Ohashi
,
H.
,
Tachibana
,
Y.
, and
Kunitomi
,
K.
,
2012
, “
Control Strategies for VHTR Gas-Turbine System With Dry Cooling
,”
ASME
Paper No. ICONE20-POWER2012-54351.
17.
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.
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