Numerical prediction of fire extinguishment characteristics of sodium leak collection tray in a fast breeder reactor
- 1. Department of Mechanical Engineering, Indian Institute of Technology Madras, Chennai 600036 (India)
- 2. Safety Engineering Division, Safety Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India)
Description
Highlights: ► Sodium fire extinguishment in a leak collection tray is modeled by lumped approach. ► Hydrodynamics of liquid sodium on tray is emulated through a draining/sloshing model. ► Pool burning rates in the tray and holdup vessel are numerically estimated. ► The model directly yields the mass of sodium recovered after extinction of fire. ► Model predictions are in reasonable agreement with the available experimental data. - Abstract: Sodium leak collection tray (LCT) is an efficient passive device used for the extinguishment of liquid sodium fire in case of an accidental leakage from the secondary circuit of a fast breeder reactor. The LCT essentially isolates the leaking sodium into closed containers where the resulting fire is extinguished due to limited availability of oxygen. The current work aims to highlight the combustion extinguishment characteristics of LCT through a lumped formulation by conserving the mass and energy of liquid sodium and constituent gases in various parts of the LCT. Here, the complex hydrodynamics of liquid sodium is emulated through a semi-analytical draining/sloshing model and its burning rates are predicted through a three-dimensional open pool combustion model for the tray region and a closed pool combustion model for the holdup vessel. These simulations evaluate the burning rates at discrete levels of liquid sodium which are subsequently interpolated to establish correlations involving instantaneous liquid levels and oxygen concentration. Using the correlations obtained from the draining and combustion models, the overall lumped formulation directly predicts the un-burnt sodium recoverable after the extinguishment of fire in the LCT. The predicted results of this model compare well with the available experimental data.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.09.015Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.09.015;
- PII
- S0029-5493(11)00808-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 12
- Journal Page Range
- p. 5189-5202
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 18. international conference on nuclear engineering
- Acronym
- ICONE-18
- Dates
- 17-21 May 2010
- Place
- Xi'an (China)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074087
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CONTAINERS; EXPERIMENTAL DATA; FBR TYPE REACTORS; FIRE EXTINGUISHERS; FIRES; GASES; HYDRODYNAMICS; LEAKS; LIQUID METALS; OXYGEN; SIMULATION; SODIUM; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; DATA; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FLUID MECHANICS; FLUIDS; INFORMATION; LIQUIDS; MECHANICS; METALS; NONMETALS; NUMERICAL DATA; REACTORS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.