**Chapter 2**

[67] Koshizuka S, Oka Y. Computational analysis of deterioration phenomena and thermal-hydraulic design of SCR. In: Proceedings of the 1st International Symposium on Supercritical Water-Cooled Reactor Design and Technology (SCR-2000), Paper No. 302. 2000

*Advanced Supercritical Fluids Technologies*

[68] Jackson JD. Consideration of the heat transfer properties of supercritical pressure water in connection with the cooling of advanced nuclear reactors. In: Proceedings of the 13th Pacific Basin Nuclear Conference (PBNC-13), Shenzhen City, China, October 21–25.

[69] Kuang B, Zhang Y, Cheng X. A new, wide-ranged heat transfer correlation of water at supercritical pressures in vertical upward ducts. In: Proceedings of the 7th International Topical Meeting

on NUclear Reactor Thermal-Hydraulics, Operations and Safety (NUTHOS-7), Seoul, Korea, October 5–

fluid flow in circular tubes. In: Proceedings of the 13th International Topical Meeting on NUclear REactor THermalhydraulics (NURETH-13),

Prefecture, Japan, September 27–

[71] Pioro I, Duffey R, Dumouchel T. Hydraulic resistance of fluids flowing in channels at supercritical pressures (survey). Nuclear Engineering and Design. 2004;**231**(2):187-197

Kanazawa City, Ishikawa

October 2. 2009

**42**

[70] Cheng X, Yang YH, Huang SF. A simple heat transfer correlation for SC

2002

9. 2008
