Published 2015 | Version v1
Book

Numerical analysis of heat transfer in rod-bundle setup

  • 1. Mechanical Engineering, Indian Institute of Technology Bombay, Mumbai (India)

Description

Heat transfer in case of Loss of Coolant Accident (LOCA) in case of an advanced reactor has been analysed in this work. The maximum temperature at any location on a heater rod was restricted to 600C. Heat removal capability for each of the boundary conditions studied was obtained using energy balance. Numerical simulation of the results for all the cases for which experiments were run were conducted using FLUENT. The rod bundle was divided into six sectors so that azimuthal symmetry could be utilized, and computational time and effort minimized. In case of an accident situation, decay heat removal happens by combined radiation and natural convection. Percentage contribution of heat transfer by each mode is obtained for each of the cases simulated. The temperature of the heater rod varies along the length hence radiation interaction with the surrounding rods is non-uniform. (author)

Part of:
Proceedings of the twenty third national heat and mass transfer conference and first international ISHMT-ASTFE heat and mass transfer conference: souvenir and book of abstracts

Additional details

Publishing Information

Publisher
Indian Space Research Organisation
Imprint Place
Trivandrum (India)
Imprint Title
Proceedings of the twenty third national heat and mass transfer conference and first international ISHMT-ASTFE heat and mass transfer conference: souvenir and book of abstracts
Imprint Pagination
269 p.
Journal Page Range
p. 189

Conference

Title
23. national heat and mass transfer conference; ISHMT-ASTFE: international heat and mass transfer conference
Acronym
IHMTC-2015
Dates
17-20 Dec 2015
Place
Trivandrum (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
48043272
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; FUEL ELEMENT CLUSTERS; LOSS OF COOLANT; NUCLEAR FACILITIES; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; FUEL ASSEMBLIES; REACTOR ACCIDENTS; REMOVAL; SAFETY

Optional Information