Experimental analyses by SIMMER-III on fuel-pin disruption and low-energy disrupted core motion
Creators
- 1. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)
Description
This paper describes experimental analyses using the SIMMER-III computer code, which is a two-dimensional multi-component multi-phase. Eulerian fluid-dynamics code. Two topics of key phenomena in core disruptive accidents were presented in this paper: fuel-pin disruption, and low energy disrupted core motion. Related experimental database were reviewed to select appropriate experiments. To analyze the fuel-pin disruption behavior, the CABRI-EFM1 and the CABRI-E7 in-pile experiments were selected. The SIMMER-III calculation was in good agreement with the overall fuel-pin disruption and dispersion behavior, which was characterized by a thermal pin-failure mode, observed in the CABRI-EFM1 experiment. Since the code framework of SIMMER-III cannot treat a mechanical deformation and breakup behavior, the SAS4A code was applied to the CABRI-E7 experiment, where a mechanical pin-failure mode was realized. In this study, such a failure mode was also reasonably simulated. The low-energy disrupted core consists principally of fuel particles and liquid steel (or fuel). Under such a mixture condition, significantly reduced melt penetration length was obtained in the THEFIS out-of-pile experiments. SIMMER-III well simulated the melt freezing and blockage behavior observed in the experiment. (author)
Availability note (English)
Available from http://dx.doi.org/10.1299/jpes.4.164Additional details
Identifiers
- DOI
- 10.1299/jpes.4.164;
Publishing Information
- Journal Title
- Journal of Power and Energy Systems
- Journal Volume
- 4
- Journal Issue
- 1
- Journal Page Range
- p. 164-179
- ISSN
- 1881-3062
Conference
- Title
- 17. international conference on nuclear engineering
- Acronym
- ICONE-17
- Dates
- 12-16 Jul 2009
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 42017720
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; FAST REACTORS; FLUID MECHANICS; FUEL PINS; MULTIPHASE FLOW; NUMERICAL ANALYSIS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; S CODES; SODIUM COOLED REACTORS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; EPITHERMAL REACTORS; FLUID FLOW; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; MATHEMATICS; MECHANICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION
Optional Information
- Notes
- 26 refs., 22 figs., 3 tabs.