CFD simulation on reactor flow mixing phenomena
Creators
- 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)
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)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48059610
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ASPECT RATIO; COMPUTER CODES; COMPUTERIZED SIMULATION; ECCS; FLUID MECHANICS; LOSS OF COOLANT; MIXING RATIO; PRESSURE DROP; PUMPS; REACTOR CORES; REACTOR SAFETY; REACTOR VESSELS; STEAM LINES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DIMENSIONLESS NUMBERS; ENGINEERED SAFETY SYSTEMS; EQUIPMENT; MECHANICS; PIPELINES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; SAFETY; SIMULATION
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.