Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
| Autor: | Yeon-Gun Lee, Eung Soo Kim, Il Woong Park, Min Seop Song |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2022 |
| Předmět: |
business.industry
Flow (psychology) Natural circulation flow TK9001-9401 MARS-KS1.5 Mechanics Computational fluid dynamics Coolant Volumetric flow rate Thermal hydraulics Natural circulation Nuclear Energy and Engineering Environmental science Head (vessel) Nuclear engineering. Atomic power business Reactor pressure vessel External reactor vessel cooling CFD analysis |
| Zdroj: | Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 72-83 (2022) |
| ISSN: | 1738-5733 |
| Popis: | This paper presents a numerical investigation of two-phase natural circulation flows established when external reactor vessel cooling is applied to a severe accident of the APR1400 reactor for the in-vessel retention of the core melt. The coolability limit due to external reactor vessel cooling is associated with the natural circulation flow rate around the lower head of the reactor vessel. For an elaborate prediction of the natural circulation flow rate using a thermal-hydraulic system code, MARS-KS1.5, a three-dimensional computational fluid dynamics (CFD) simulation is conducted to estimate the flow rate and pressure distribution of a liquid-state coolant at the brink of significant void generation. The CFD calculation results are used to determine the loss coefficient at major flow junctions, where substantial pressure losses are expected, in the nodalization scheme of the MARS-KS code such that the single-phase flow rate is the same as that predicted via CFD simulations. Subsequently, the MARS-KS analysis is performed for the two-phase natural circulation regime, and the transient behavior of the main thermal-hydraulic variables is investigated. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|