Nuclear power becomes more and more important in many countries worldwide as a basis for current and future electrical energy generation. The largest group of operating nuclear power plants (NPPs) equipped with water-cooled reactors (96% of all NPPs) has gross thermal efficiencies ranging from 30–36%. Such relatively low values of thermal efficiencies are due to lower pressures/temperatures at the inlet to a turbine (4.57.8MPa/257293°C). However, modern combined-cycle power plants (Brayton gas-turbine cycle and subcritical-pressure steam Rankine cycle, fueled by natural gas) and supercritical-pressure coal-fired power plants have reached gross thermal efficiencies of 62% and 55%, respectively. Therefore, next generation or Generation IV NPPs with water-cooled reactors should have thermal efficiencies as close as possible to those of modern thermal power plants. A significant increase in thermal efficiencies of water-cooled NPPs can be possible only due to increasing turbine inlet parameters above the critical point of water, i.e., supercritical water-cooled reactors (SCWRs) have to be designed. This path of increasing thermal efficiency is considered as a conventional way that coal-fired power plants followed more than 50 years ago. Therefore, an objective of the current paper is a study on neutronics and thermalhydraulics characteristics of a generic 1200-MWel pressure-channel (PCh) SCWR. Standard neutronics codes DRAGON and DONJON have been coupled with a new thermalhydraulics code developed based on the latest empirical heat-transfer correlation, which allowed for more accurate estimation of basic characteristics of a PCh SCWR. In addition, the computational fluid dynamics (CFD) Fluent code has been used for better understanding of the specifics of heat transfer in supercritical water. Future studies will be dedicated to materials and fuels testing in an in-pile supercritical water loop and developing passive safety systems.

References

1.
Pioro
,
I.
, and
Kirillov
,
P.
,
2013
, “Current Status of Electricity Generation in the World,”
Materials and Processes for Energy: Communicating Current Research and Technological Developments
(
Energy Book Series
, Vol.
1
), A. Méndez-Vilas, ed.,
Formatex Research Center
,
Spain
, pp.
783
795
.
2.
Pioro
,
I.
,
2012
, “Nuclear Power as a Basis for Future Electricity Production in the World,”
Current Research in Nuclear Reactor Technology in Brazil and Worldwide
,
A.
Mesquita
and
H.
Rezende
, eds.,
INTECH
,
Rijeka, Croatia
, pp.
211
250
.
3.
Pioro
,
I.
, and
Kirillov
,
P.
,
2013
, “Current Status of Electricity Generation at Thermal Power Plants,”
Materials and Processes for Energy: Communicating Current Research and Technological Developments
(
Energy Book Series
, Vol.
1
), A. Méndez-Vilas, ed.,
Formatex Research Center
,
Spain
, pp.
796
805
.
4.
Pioro
,
I.
, and
Kirillov
,
P.
,
2013
, “Current Status of Electricity Generation at Nuclear Power Plants,”
Materials and Processes for Energy: Communicating Current Research and Technological Developments
(
Energy Book Series
, Vol.
1
), A. Méndez-Vilas, ed.,
Formatex Research Center
,
Spain
, pp.
806
817
.
5.
Pioro
,
I.
, and
Kirillov
,
P.
,
2013
, “Generation IV Nuclear Reactors as a Basis for Future Electricity Production in the World,”
Materials and Processes for Energy: Communicating Current Research and Technological Developments
(
Energy Book Series
, Vol.
1
), A. Méndez-Vilas, ed.,
Formatex Research Center
,
Spain
, pp.
818
830
.
6.
Pioro
,
I.
, and
Duffey
,
R.
,
2007
,
Heat Transfer and Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications
,
ASME Press
,
New York
,
334
pp.
7.
Pioro
,
I.
,
2011
, “The Potential Use of Supercritical Water-Cooling in Nuclear Reactors,”
Nuclear Energy Encyclopedia: Science, Technology, and Applications
, S. Krivit, J. Lehr, and T. Kingery, eds.,
John Wiley & Sons
,
Hoboken, NJ
, pp.
309
347
.
8.
Naidin
,
M.
,
Mokry
,
S.
,
Baig
,
F.
, et al.,
2009
, “
Thermal-Design Options for Pressure-Channel SCWRs with Co-Generation of Hydrogen
,”
J. Eng. Gas Turb Power
,
131
(
Jan.
),
8
p.
9.
Peiman
,
W.
,
Pioro
,
I.
, and
Gabriel
,
K.
,
2012
, “Thermal Aspects of Conventional and Alternative Fuels in SuperCritical Water-Cooled Reactor (SCWR) Applications,”
Nuclear Reactors
, A. Z. Mesquita, ed.,
INTECH
,
Rijeka, Croatia
, pp.
123
156
.
10.
Peiman
,
W.
,
Pioro
,
I.
, and
Gabriel
,
K.
,
2013
, “
Thermal Design Aspects of High-Efficiency Channel for SuperCriticalWater-cooled Reactors (SCWRs)
,”
Nucl. Eng. Design
,
264
(
Nov.
), pp.
238
245
.10.1016/j.nucengdes.2013.02.021
11.
Pioro
,
I.
2014
, “Application of Supercritical Pressures in Power Engineering: Specifics of Thermophysical Properties and Forced-Convective Heat Transfer,”
Supercritical Fluid Technology for Energy and Environmental Applications
V. Anikeev and M. Fan, eds.,
Elsevier
,
Amsterdam
, pp.
201
233
.
12.
Pioro
,
I.
, and
Mokry
,
S.
,
2011
, “Thermophysical Properties at Critical and Supercritical Conditions,”
Heat Transfer: Theoretical Analysis, Experimental Investigations and Industrial Systems
, A. Belmiloudi, ed.,
INTECH
,
Rijeka, Croatia
, pp.
573
592
.
13.
Pioro
,
I.
, and
Mokry
,
S.
,
2011
, “Heat Transfer to Fluids at Supercritical Pressures,”
Heat Transfer: Theoretical Analysis, Experimental Investigations and Industrial Systems
, A. Belmiloudi, ed.,
INTECH
,
Rijeka, Croatia
, pp.
481
504
.
14.
Mokry
,
S.
,
Pioro
,
I.
,
Farah
,
A.
, et al.,
2011
, “
Development of Supercritical Water Heat-Transfer Correlation for Vertical Bare Tubes
,”
Nucl. Eng. Design
,
241
(
4
), pp.
1126
1136
.10.1016/j.nucengdes.2010.06.012
15.
Zahlan
,
H.
,
Groeneveld
,
D. C.
,
Tavoularis
,
S.
, et al.,
2011
, “
Assessment of Supercritical Heat Transfer Prediction Methods
,”
Proceedings of the 5th International Symposium on SCWR (ISSCWR-5)
,
Vancouver, BC, Canada
, Mar. 13–16, Paper No. P008,
20
pp.
16.
Saltanov
,
E.
, and
Pioro
,
I.
,
2011
, “
World Experience in Nuclear Steam Reheat
,”
Nuclear Power: Operation, Safety and Environment
, P. V. Tsvetkov ed.,
INTECH
,
Rijeka, Croatia
, pp.
3
28
.
17.
Dragunov
,
A.
,
Saltanov
,
E.
,
Pioro
,
I.
, et al.,
2013
, “
Investigation of Thermophysical and Nuclear Properties of Prospective Coolants for Generation-IV Nuclear Reactors
,”
Proceedings of the 21st ICONE
,
July 29–Aug. 2
,
Chengdu, China
, Paper No. 16020,
11
pp.
18.
Marleau
,
G.
,
Hébert
,
A.
, and
Roy
,
R.
,
2011
,
A User Guide for DRAGON Version 4
.
19.
Sekki
,
D.
,
Hébert
,
A.
, and
Chambon
,
R.
,
2011
,
A User Guide for DONJON Version 4
.
20.
National Institute of Standards and Technology
,
2010
,
NIST Reference Fluid Thermodynamic and Transport Properties–REFPROP
,
NIST Standard Reference Database 23, Ver. 9.0.
,
Department of Commerce
, Boulder, CO.
21.
Peiman
,
W.
,
Saltanov
,
E.
,
Pioro
,
I.
, and
Gabriel
,
K.
,
2012
, “
Pressure Drop Analysis in a Pressure-Tube Supercritical Water-Cooled Reactor
,”
Trans. European Nuclear Conference (ENC-2012)
,
Manchester, UK
,
Dec. 9–12
, Paper No. ENC2012-A0258,
8
pp.
22.
Farah
,
A.
,
Harvel
,
G.
, and
Pioro
,
I.
,
2013
,
Assessment of Fluent Code as a Tool for SCW Heat Transfer Analysis
,
Proceedings of the 21st ICONE
,
July 29–Aug. 2
,
Chengdu, China
, Paper No. 16446,
9
pp.
23.
ANSYS, Inc.
,
2009
,
ANSYS FLUENT 12.1 in Workbench User’s Guide
.
24.
Miletić
,
M.
,
Růžičková
,
M.
,
Fukač
,
R.
, et al.,
2013
, “
Supercritical-Water Experimental Setup for In-Pile Operation
,”
Nucl. Eng. Design
,
259
, pp.
166
171
.10.1016/j.nucengdes.2013.02.045
25.
Samuel
,
J.
,
Harvel
,
G.
, and
Pioro
,
I.
,
2013
, “
Numerical Analysis of Natural Circulation Phenomena of Supercritical Fluids
,”
Proceedings of the 21st ICONE
,
July 29–Aug. 2
,
Chengdu, China
, Paper No. 16452,
10
pp.
26.
Oka
,
Y.
,
Koshizuka
,
S.
,
Ishiwatari
,
Y.
, and
Yamaji
,
A.
,
2010
,
Super Light Water Reactors and Super Fast Reactors
,
Springer
,
New York
,
416
pp.
27.
Schulenberg
,
T.
, and
Starflinger
,
J.
, Eds.,
2012
, “High Performance Light Water Reactor,”
Design and Analyses
,
KIT Scientific Publishing
,
Germany
,
241
pp.
You do not currently have access to this content.