Published 2009 | Version v1
Miscellaneous

Development and validation of unstructured adaptive mesh technique for gas-liquid two-phase flows

  • 1. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)
  • 2. Kyoto University, Graduate School of Engineering, Kyoto (Japan)

Description

For the purpose of direct numerical simulations of gas entrainment (GE) phenomenon in sodium-cooled fast reactors, a high-precision numerical simulation method for gas-liquid two-phase flows have been developed. To reproduce the GE phenomenon by numerical simulations, there are three key issues, i.e. geometry dependency, interfacial dynamics and locality. Former two issues are already addressed by employing an unstructured mesh and a high-precision simulation method for gas-liquid two-phase flow, respectively. In addition, the locality of the GE phenomenon has been addressed by developing an unstructured adaptive mesh technique by which high mesh resolutions can automatically applied transiently to the occurrence regions of the GE phenomenon. As for single-phase flows, it has been confirmed that the unstructured adaptive mesh technique is efficient to simulate vortices with less computational costs than that on non-adaptive meshes. In this paper, the unstructured adaptive mesh technique is extended to two-phase flows. For that purpose, the redistribution algorithms for two-phase flow variables are developed based on the conservation laws of the variables. Finally, the unstructured adaptive mesh technique is validated by solving the well-known slotted-disk revolution and dam-break problems. As a result, the adaptive mesh technique succeeds in maintaining the slotted-disk shape after one revolution by using relatively small number of cells. The interfacial dynamics in the dam-break problem is also resolved well on the unstructured adaptive mesh. (author)

Part of:
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Imprint Title
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[4617 p.]
Journal Page Range
[13 p.]

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa, Ishikawa (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
43036764
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; ENTRAINMENT; GAS FLOW; GASES; INTERFACES; LIQUID FLOW; LMFBR TYPE REACTORS; MESH GENERATION; SODIUM COOLED REACTORS; TWO-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VALIDATION; VOLUME
Descriptors DEC
BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FLUIDS; LIQUID METAL COOLED REACTORS; REACTORS; SIMULATION; TESTING

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1316.pdf