Study on Thermal Characteristics of Water-Rod in SCWR

Abstract:

Water-rod is introduced into Supercritical Water Cooled Reactor (SCWR) to guarantee the homogeneous distribution of core axial power, and there could be many types of flow in water-rod. Based on three types of water-rod and flow, which named S type, D1 type, and D2 type, choosing different values of structural parameters and material thermal conductivity, the distributions of moderator density and average density in each case are obtained through making program to associated-calculate the fuel rod, coolant and moderator. The results indicate that considering only moderator density, the D2 type double water-rod which has smaller thermal conductivity and bigger outer length of inner water-rod is the best choice; considering average density, both the S type single water-rod and the D2 type double water-rod which have smaller thermal conductivity and smaller outer length of inner water-rod is the best choice; the thermal performance of D1 type double water-rod is inferior because of its inherent defect, so it is not suitable for use.

• Periodical: Advanced Materials Research (Volumes 512-515)
• Pages: 869-873
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.512-515.869
• Online since: May 2012
• Authors: Tao Zhou, Can Hui Sun, Wan Xu Cheng
• Keywords: Supercritical Water Cooled Reactor, Thermal, Type of Flow, Water-Rod

References

[1] U.S: DOE Nuclear Energy Research Advisory Committee, the Generation IV International Forum. A Technology Roadmap for Generation IV Nuclear Energy Systems, GIF-002-00,2002,12.

DOI: 10.2172/859029

[2] X. Cheng, X.J. Liu: Atomic Energy Science and Technology, 2008,42(2), p.167 (in Chinese).

[3] Z.Y. Li, T. Zhou, C.H. Sun: Nuclear Power Engineering, 2011,32(3), p.52 (in Chinese).

[4] C.H. Sun, T. Zhou, Z.Y. Li: Atomic Energy Science and Technology, 2010,44(S), p.346 (in Chinese).

[5] C.H. Sun, T. Zhou, Z.S. Hou, etc: Advanced Materials Research, 2012, 347-353, p.1633.

[6] X.J. Liu, T. Yang, X. Cheng: Annals of Nuclear Energy, 2010,37, p.1674.

[7] T. Schulenberg, J. Starflinger, J. Heinecke: Nuclear Energy, 2008, 50, p.526.

[8] O. Yasushi, K. Seiichi, O. Yoshiaki: Journal of NUCLEAR SCIENCE and TECHOLOGY, 1996,33(5) , p.365.

[9] A. Yamaji, Y. Oka, S. Koshizuka: Journal of Nuclear Science and Technology, 2005, 42(1),p.8.

[10] J. Hofmeister, C. Waata, J. Starflinger, et al: Nuclear Engineering and Design, 2007, 237, p.1513.

[11] A. Yamaji, K. Kamei, Y. Oka, et al: Annals of Nuclear Energy, 2005,32, p.651.

[12] K. Kamei, A. Yamaji, Y. Ishiwatari, et al: Fuel and core design of super LWR with stainless steel cladding, Proceeding of ICAPP'05. 2005.