Published November 2016 | Version v1
Miscellaneous

CFD simulation on reactor flow mixing phenomena

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

A pre-test calculation for multi-dimensional flow mixing in a reactor core and downcomer has been studied using a CFD code. To study the effects of Reactor Coolant Pump (RCP) and core zone on the boron mixing behaviors in a lower downcomer and core inlet, a 1/5-scale CFD model of flow mixing test facility for the APR+ reference plant was simulated. The flow paths of the 1/5-scale model were scaled down by the linear scaling method. The aspect ratio (L/D) of all flow paths was preserved to 1. To preserve a dynamic similarity, the ratio of Euler number was also preserved to 1. A single phase water flow at low pressure and temperature conditions was considered in this calculation. The calculation shows that the asymmetric effect driven by RCPs shifted the high velocity field to the failed pump's flow zone. The borated water flow zone at the core inlet was also shifted to the failed RCP side. (author)

Part of:
Proceedings of the 10th Japan-Korea symposium on nuclear thermal hydraulics and safety (NTHAS10)

Additional details

Publishing Information

Imprint Title
Proceedings of the 10th Japan-Korea symposium on nuclear thermal hydraulics and safety (NTHAS10)
Imprint Pagination
592 p.
Journal Page Range
5 p.

Conference

Title
10. Japan-Korea symposium on nuclear thermal hydraulics and safety
Acronym
NTHAS10
Dates
27-30 Nov 2016
Place
Kyoto (Japan)

Optional Information

Notes
Available as USB Flash Memory Data in PDF format, Paper ID: NTHAS10_sub_data/pdf/N10P1034.pdf; 9 refs., 7 figs., 1 tab.