Fractional scaling analysis of cladding temperature in large break loss of coolant accident

Author:

Yan B.H.,Long B.,Li L.G.,Xing J.,Lu D.H.

Publisher

Elsevier BV

Reference18 articles.

1. Bestion, D., D’Auria, F., Nakamura, H. et al. 2017. Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design: a State-of-the-Art Report. OECD Nuclear Energy Agency.

2. Fractional scaling method applied to a pressurizer test facility;Botelho;Prog. Nucl. Energ.,2010

3. Catton, I., Wulff, W., Zuber, N. et al. 2005. Application of Fractional Scaling Analysis (FSA) to Loss of Coolant Accidents (LOCA) – Part 3. In: The 11th International Topical Meeting on Nuclear Reactor Thermal–Hydraulics (NURETH-11), Avignon, France, 2005.

4. Westinghouse Electric Company LLC. AP1000 PIRT and Scaling Assessment. DCP/NRC 1480. 2001.

5. Guangdong Nuclear Power Training Center. 2004. Device and systems of 900 MW PWR. Atomic energy press.

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