The supercritical water-cooled reactor (SWCR) has been selected as one of the most promising reactors for Generation IV nuclear reactors due to its higher thermal efficiency and more simplified structure compared to the state-of-the-art light water reactors (LWRs). However, there are a large number of potential problems that must be addressed, particularly the fuel assembly design of the SCWR. SCWRs are a kind of high-temperature, high-pressure, water-cooled reactor that operates above the thermodynamic critical point of water (374°C, 22.1 MPa). Corrosion and degradation of materials used in supercritical water environments are determined by several environment- and material-dependent factors. In particular, irradiation-induced changes in microstructure and microchemistry are major concerns in a nuclear reactor. Many structural materials including alloys and ceramics have been proposed for use as SCWR components or materials for applying protective coatings in SCWRs. In this paper, the present status of supercritical fuel assembly design at home and abroad is reported. According to the special requirements of supercritical core design, a kind of configuration design of fuel assembly with two-flow core and using SiC as cladding material are proposed. The analysis results have shown that the design basically meets the requirements of fuel assembly design, which has good feasibility and performance.

References

1.
Bloom
,
E. E.
,
1998
, “
The Challenge of Developing Structural Materials for Fusion Power Systems
,”
J. Nucl. Mater.
,
263
(
Part A
), pp. 
7
17
. 0022-311510.1016/S0022-3115(98)00352-3
2.
Senor
,
D. J.
,
Youngblood
,
G. E.
,
Moore
,
C. E.
,
Trimble
,
D. J.
,
Newsome
,
G. A.
, and
Woods
,
J. J.
,
1996
, “
Effects of Neutron Irradiation on Thermal Conductivity of SiC-Based Composites and Monolithic Ceramics
,”
Fusion Technol.
,
30
(
3 Part 2A
), pp. 
943
955
.
3.
Reiss
,
T.
,
Csom
,
Gy.
, and
Feher
,
S.
,
2010
, “
The Simplified Supercritical Water-Cooled Reactor (SSCWR), a New SCWR Design
,”
Prog. Nucl. Energy
,
52
(
2
), pp. 
177
189
. 0149-197010.1016/j.pnucene.2009.06.006
4.
Yamaji
,
A.
,
Kamai
,
K.
,
Oka
,
Y.
, and
Koshizuka
,
S.
,
2005
, “
Improved Core Design of the High Temperature Supercritical-Pressure Light Water Reactor
,”
Ann. Nucl. Energy
,
32
(
7
), pp. 
651
670
.
5.
Schulenberg
,
T.
,
Starflinger
,
J.
,
Marsault
,
P.
,
Bittermann
,
D.
,
Maraczy
,
C.
,
Laurien
,
E.
,
Lycklama à Nijeholtf
,
J. A.
,
Anglartg
,
H.
,
Andreanih
,
M.
,
Ruzickovai
,
M.
,
Toivonenj
,
A.
,
2011
, “
European Supercritical Water Cooled Reactor
,
Nucl. Eng. Des.
,
241
(
9
),
3505
3513
. 0029-549310.1016/j.nucengdes.2010.09.039
6.
Fischer
,
K.
,
Schulenberg
,
T.
, and
Laurien
,
E.
,
2009
, “
Design of a Supercritical Water-Cooled Reactor With a Three-Pass Core Arrangement
,”
Nucl. Eng. Des.
,
239
(
4
),
800
812
. 0029-549310.1016/j.nucengdes.2008.12.019
7.
Barringer
,
E.
,
Faiztompkins
,
Z.
, and
Feinroth
,
H.
,
2007
, “
Corrosion of CVD Silicon Carbide in 500°C Supercritical Water
,”
J. Am. Ceram. Soc.
,
90
(
1
),
315
318
. 0002-782010.1111/jace.2007.90.issue-1
8.
Leung
,
L.
,
2015
, “
Status of Canadian Generation IV National Program in Support of SCWR Concept Development
,”
ISSCWR-7, March 2015
,
Helsinki, Finland
.
9.
Ahn
,
K.
,
2006
, “
Comparison of Silicon Carbide and Zircaloy4 Cladding during LBLOCA
,”
Massachusetts Institute of Technology Department of Nuclear Science and Engineering
, 4.
10.
Yueh
,
K.
,
Carpenter
,
D.
, and
Feinroth
,
H.
,
2010
, “
Clad in Clay
,”
Nucl. Eng. Int.
,
55
(
666
), pp.
14
16
. 0029-5507
11.
Kim
,
W. J.
,
Kim
,
D. J.
, and
Park
,
J. Y.
,
2013
, “
Fabrication and Material Issues for the Application of SiC Composites to LWR Fuel Cladding
,”
Nucl. Eng. Technol.
,
45
(
4
), pp. 
565
572
.10.5516/NET.07.2012.084
12.
Hofmeister
,
J.
,
Waata
,
C.
, and
Starflinger
,
J.
,
2007
, “
Fuel Assembly Design Study for a Reactor with Supercritical Water
,”
Nucl. Eng. Des.
,
237
(
14
), pp. 
1513
1521
. 0029-549310.1016/j.nucengdes.2007.01.008
You do not currently have access to this content.