Published December 2011 | Version v1
Journal article

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.2011.09.015

Additional 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.