Supercritical Water-Cooled ReactorsView this Special Issue
Editorial | Open Access
Supercritical Water-Cooled Reactors
Supercritical water-cooled reactor (SCWR) is the water-cooled reactor using supercritical pressure water as coolant . It is considered as one of the promising Generation IV reactors, due to its advantages of plant simplification and high thermal efficiency [2, 3].
Several design concepts of SCWRs have been proposed: (a) supercritical water-cooled thermal neutron reactor; (b) supercritical water-cooled fast neutron reactor; (c) supercritical water-cooled mixed neutron spectrum reactor; (d) supercritical water-cooled pebble bed reactor; (e) supercritical heavy-water-cooled reactor. The detailed design parameters of some typical SCWR concepts around the world are summarized in Table 1 . Recently, the use of thorium in the SCWRs has been investigated [5, 6].
Now the special issue is published, which includes 5 papers. The contents include a new concept of core design, like “A simplified supercritical fast reactor with thorium fuel,” calculation code development, like “Preliminary development of thermal power calculation code H-power for a supercritical water reactor,” “Code development in coupled PARCS/RELAP5 for supercritical water reactor,” and flow distribution, one of the important issues of thermal hydraulics in the nuclear reactor, like “Core flow distribution from coupled supercritical water reactor analysis.” It also contains some experimental results, like “Experimental investigation on flow-induced vibration of fuel rods in supercritical water loop.” We hope that readers of this special issue will find not only the development status of SCWRs and updated reviews on SCWRs, but also the formulation of important questions to be resolved such as how to develop the codes for SCWRs.
- Y. Oka, S. Koshizuka, Y. Ishiwatari, and A. Yamaji, Super Light Water Reactors and Super Fast Reactors, Springer, New York, NY, USA, 2010.
- S. Liu and J. Cai, “Convergence analysis of neutronic/thermohydraulic coupling behavior of SCWR,” Nuclear Engineering and Design, vol. 265, pp. 53–62, 2013.
- S. Liu and J. Cai, “Neutronic and thermohydraulic characteristics of a new breeding thorium-uranium mixed SCWR fuel assembly,” Annals of Nuclear Energy, vol. 62, no. 1, pp. 429–436, 2013.
- X. Yang, G. H. Su, W. Tian, J. Wang, and S. Qiu, “Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition,” Annals of Nuclear Energy, vol. 37, no. 12, pp. 1723–1734, 2010.
- S. Liu and J. Cai, “Neutronics assessment of thorium-based fuel assembly in SCWR,” Nuclear Engineering and Design, vol. 260, pp. 1–10, 2013.
- S. Liu and J. Cai, “Design & optimization of two breeding thorium-uranium mixed SCWR fuel assemblies,” Progress of Nuclear Energy, vol. 70, pp. 6–19, 2014.
- Ph. Marsault, C. Renault, G. Rimpault, P. Dumaz, and O. Antoni, “Pre-design studies of SCWR in fast neutron spectrum: evaluation of operating conditions and analysis of the behavior in accidental situations,” in Proceedings of the International Conference of Asian Political Parties (ICAPP '04), Pittsburgh, Pa, USA, June 2004.
Copyright © 2014 Jiejin Cai et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.