Development of numerical simulation method for molten fuel falling behavior based on detailed two-phase analysis code TPFIT
- 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
- 2. University of Tsukuba, Tsukuba, Ibaraki (Japan)
Description
In order to improve the safety of the BWR, it is required to evaluate the behavior of the plant when a severe accident occurred as seen at the Fukushima Daiichi NPPs. The objective of this study is to develop the evaluation method of the characteristics of molten core jet including the effects of the complicated structures in the BWR lower plenum. In this development, we are developing a simulation method to estimate the behavior of molten core jet falling down to the lower plenum of the BWR based on interface tracking method code TPFIT. In this paper, to validate the applicability of the modified TPFIT to the jet breakup phenomena, numerical results were compared with experimental results in detail. As a results, it was confirmed that the applicability of the modified TPFIT to the interface shape of the tip at initial stage of jet breakup, and atomization occurring at the interfaces. (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
- 6 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
- 48059617
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; ENERGY CONSERVATION; FLUID MECHANICS; FRAGMENTATION; GUIDE TUBES; MELTDOWN; REACTOR CORES; REACTOR SAFETY; SHEAR PROPERTIES; SURFACE TENSION; TWO-PHASE FLOW; VISCOSITY
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID FLOW; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SURFACE PROPERTIES; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Paper ID: NTHAS10_sub_data/pdf/N10P1061.pdf; 6 refs., 6 figs., 2 tabs.