An Experimental Evaluation of the APR1000 Core Flow Distribution Using a 1/5 Scale Model

Author:

Kim Kihwan1ORCID,Kim Woo-Shik1ORCID,Choi Hae-Seob1,Seol Hyosung1,Lim Byung-Jun1,Euh Dong-Jin1

Affiliation:

1. Atomic Energy Research Institute, 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon 34057, Republic of Korea

Abstract

The experimental data of core flow distribution are indispensable for obtaining licensing and facilitating the design of fluid systems of nuclear reactors. In this study, an Advanced power reactor Core flow and Pressure (ACOP) test facility was established to experimentally simulate the internal flow of the Advanced Power Reactor 1000 (APR1000) on a reduced length scale of 1/5. The core region was simulated by using 177 core simulators representing the fuel assemblies of the APR1000. The APR1000 flow distributions were synthetically identified by accurately measured parameters: the core inlet flow rate and outlet pressure under the four-pump balanced and unbalanced flow conditions. The overall inlet flow rates ranged from 87.7% to 112.0% relative to the averaged flow rate. Here, we scrutinize the flow distributions considering the flow conditions and internal structures and briefly describe the applied scaling method and design concept of the test facility.

Funder

Korean Government

Publisher

MDPI AG

Reference11 articles.

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4. Song, C.-H., Kwon, T.S., Yun, B.J., Choi, K.Y., Kim, H.Y., and Jun, H.G. (2010, January 17–21). Thermal-Hydraulic R&Ds for the APR+ Developments in Korea. Proceedings of the ICONE18, Xi’an, China.

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