Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly

Author:

Liu X.J.,Cheng X.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

1. Buongiorno, J., MacDonald, P., 2003. Study of solid moderators for the thermal-spectrum supercritical water-cooled reactor. In: 11th International Conference on Nuclear Engineering (ICONE 11), Tokyo, Japan.

2. Bae, Y.Y., Hyung, K.J., Jang, J., et al., 2004. Research of a supercritical pressure water cooled reactor in Korea. In: Proceedings of International Congress on Advanced Nuclear Power Plants 2004 (ICAPP’ 04), Pittsburgh, USA.

3. Cheng, X., Schulenberg, T., Koshizuka, S., 2002. Thermal-hydraulic analysis of supercritical pressure light water reactors. In: Proceedings of International Congress on Advanced Nuclear Power Plants 2002 (ICAPP’ 02), Hollywood, Florida.

4. Design analysis of core assemblies for supercritical pressure conditions;Cheng;Nuclear Engineering and Design,2003

5. Numerical analysis of heat transfer in supercritical water-cooled flow channels;Cheng;Nuclear Engineering and Design,2007

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