Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core-Reference-Cited by-同舟云学术

Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core

Published:2015-12-09 Issue:1 Volume:2 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Yetisir Metin¹,Xu Rui¹,Gaudet Michel¹,Movassat Mohammad¹,Hamilton Holly²,Nimrouzi Mohammedhossein³,Goldak John A.³

Affiliation:

1. Fluid Sealing Technology, Canadian Nuclear Laboratories Limited, Chalk River Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada e-mail:

2. Fuel Development Branch, Canadian Nuclear Laboratories Limited, Chalk River Laboratories, 286 Plant Road, Chalk River, ON K0J 1J0, Canada

3. Mechanical and Aerospace Engineering, Carleton University, 1125 Colonel By Dr., Ottawa, ON K1S 5B6, Canada e-mail:

Abstract

The Canadian Supercritical Water-Cooled Reactor (SCWR) is a 1200 MW(e) channel-type nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a low-pressure heavy water moderator and calandria vessel containment. The supercritical water (SCW) coolant flows into the fuel channels through a common inlet plenum and exits through a common outlet header. One of the main features of the Canadian SCWR concept is the high-pressure (25 MPa) and high-temperature (350°C at the inlet, 625°C at the outlet) operating conditions that result in an estimated thermal efficiency of 48%. This is significantly higher than the thermal efficiency of the present light water reactors, which is about 33%. This paper presents a description of the Canadian SCWR core design concept; various numerical analyses performed to understand the temperature, flow, and stress distributions of various core components; and how the analyses results provided input for improved concept development.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4031247/6066235/ners_2_1_011007.pdf

Reference9 articles.

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2. Yetisir, M., Gaudet, M., and Rhodes, D., 2013, “Development and Integration of Canadian SCWR With Counter-Flow Fuel Channel,” 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6), Shenzhen, Guangdong, China.

3. Fischer, K., Laurien, E., Class, A., and Schulenberg, T., 2007, “Design and Optimization of a Backflow Limiter for the High Performance Light Water Reactor,” Proceedings of GLOBAL 07, Boise, ID.

4. Nimrouzi, M. 2014, “A Methodology for Optimal Design of the Canadian SCWR Reactor Core,” M.Sc. thesis, Carleton University.

5. Pencer, J., Watts, D., Colton, A., Wang, X., Blomeley, L., Anghel, V., and Yue, S., 2013, “Core Neutronics for the Canadian SCWR Conceptual Design,” The 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6), Shenzhen, Guangdong.

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