Analysis stabilization technique of nuclear power plant simulation system
Description
The plant simulator is required to be capable of simulating accident events stably and accurately, particularly for applications to an operation support system for plant accident events. The simulation system has a three-dimensional neutron calculation, a two-phase flow calculation, a fuel rod temperature calculation, and a control-block calculation. The two-phase flow calculation uses a two-phase flow stabilized calculation model to cover a wide pressure range. The two-phase flow calculation includes the virtual mass term and an explicit diffusion term to remove numerical instability. And in particular for the low pressure and large diameter flow channel conditions, the interfacial shear model was developed using experimental data and it was applied in the two-phase flow calculation. We evaluated effect of the stabilization by the steady-state two-phase flow analysis in a vertical pipe and confirmed that the stability of the analysis was sufficiently good and the void fraction was predicted accurately in the pressure range from 0.5 MPa to 7.2 MPa by introducing the explicit diffusion term and the developed interfacial shear model for the low pressure and the large diameter flow channel. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
- Imprint Pagination
- [3737 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 23. international conference on nuclear engineering
- Acronym
- ICONE-23
- Dates
- 17-21 May 2015
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48051398
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN-BASIS ACCIDENTS; DIFFUSION; FUEL RODS; HEAT TRANSFER; MASS TRANSFER; NUCLEAR POWER PLANTS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; STABILIZATION; THERMAL HYDRAULICS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; DIFFERENTIAL EQUATIONS; ENERGY TRANSFER; EQUATIONS; FLUID FLOW; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-1601.pdf; 12 refs., 7 figs.