Numerical Study on Two-phase Natural Circulation Flow by External Reactor Vessel Cooling of iPOWER
Creators
- 1. Jeju National University, Jeju (Korea, Republic of)
- 2. KHNP Central Reaserch Institute, Daejeon (Korea, Republic of)
Description
The domestic innovative power reactor named iPOWER will employ the passive molten corium cooling system(PMCCS) to cool down and stabilize the core melt in the severe accident. The final design concept of the PMCCS is yet to be determined, but the in-vessel retention through external reactor vessel cooling has been also considered as a viable strategy to cope with the severe accident. In this study, the two-phase natural circulation flow established between the reactor vessel and the insulation was simulated using a thermal-hydraulic system code, MARS-KS. The flow path of cooling water was modeled with one-dimensional nodes, and the boundary condition of the heat load from the molten core was defined to estimate the naturally-driven flow rate. The evolution of major thermal-hydraulic parameters were also evaluated, including the temperature and the level of cooling water, the void fraction around the lower head of the reactor vessel, and the heat transfer mode on its external surface.
Additional details
Publishing Information
- Journal Title
- Journal of Energy Engineering (Korea. Print)
- Journal Volume
- 28
- Journal Issue
- 4
- Series
- 7 refs, 11 figs, 2 tabs
- Journal Page Range
- p. 103-110
- ISSN
- 1598-7981
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 52085120
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- HEAT TRANSFER; M CODES; MELTDOWN; NATURAL CONVECTION; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; ONE-DIMENSIONAL CALCULATIONS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; SEVERE ACCIDENTS; SIMULATION; THERMAL HYDRAULICS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; CONTAINERS; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATHEMATICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SEVERE ACCIDENTS; THERMAL POWER PLANTS