Research Papers

Fuel Assembly Design for Supercritical Water-Cooled Reactor

[+] Author and Article Information
Feng Linna

Science and Technology on Reactor System Design Technology Laboratory,
Third Section of Huafu Road, Huayang Town, Shuangliu County, Chengdu,
Sichuan Province 610213, China
e-mail: flnrever@sina.com

Zhu Fawen

Science and Technology on Reactor System Design Technology Laboratory,
Third Section of Huafu Road, Huayang Town, Shuangliu County, Chengdu,
Sichuan Province 610213, China
e-mail: 254085634@qq.com

Manuscript received March 31, 2015; final manuscript received June 8, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011014 (Dec 09, 2015) (6 pages) Paper No: NERS-15-1040; doi: 10.1115/1.4030797 History: Received March 31, 2015; Accepted June 08, 2015

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.

Copyright © 2015 by ASME
Your Session has timed out. Please sign back in to continue.


Bloom, E. E., 1998, “The Challenge of Developing Structural Materials for Fusion Power Systems,” J. Nucl. Mater., 263(Part A), pp. 7–17. 0022-3115 10.1016/S0022-3115(98)00352-3
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.
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. 0149-1970 10.1016/j.pnucene.2009.06.006
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. [CrossRef]
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. 0029-5493 10.1016/j.nucengdes.2010.09.039
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. 0029-5493 10.1016/j.nucengdes.2008.12.019
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. 0002-7820 10.1111/jace.2007.90.issue-1
Leung, L., 2015, “Status of Canadian Generation IV National Program in Support of SCWR Concept Development,” ISSCWR-7, March 2015, Helsinki, Finland.
Ahn, K., 2006, “Comparison of Silicon Carbide and Zircaloy4 Cladding during LBLOCA,” Massachusetts Institute of Technology Department of Nuclear Science and Engineering, 4.
Yueh, K., Carpenter, D., and Feinroth, H., 2010, “Clad in Clay,” Nucl. Eng. Int., 55(666), pp. 14–16. 0029-5507
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
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. 0029-5493 10.1016/j.nucengdes.2007.01.008


Grahic Jump Location
Fig. 1

SCLWR-H fuel assembly in Japan

Grahic Jump Location
Fig. 2

HPLWR fuel assembly in Europe

Grahic Jump Location
Fig. 3

CANDU-SCWR fuel assembly in Canada

Grahic Jump Location
Fig. 4

2×2 Assembly cluster in China

Grahic Jump Location
Fig. 5

Two-pass core design and core flow distribution

Grahic Jump Location
Fig. 6

Illustration of (a) fuel assembly cluster and (b) fuel rod

Grahic Jump Location
Fig. 7

Position illustration of fuel rod: (a) upper position and (b) lower position

Grahic Jump Location
Fig. 8

Head piece of fuel assembly cluster

Grahic Jump Location
Fig. 9

Foot piece of fuel assembly cluster




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