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Experimental investigations on decay heat removal in advanced nuclear reactors using single heater rod test facility: Air alone in the annular gap

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Title Experimental investigations on decay heat removal in advanced nuclear reactors using single heater rod test facility: Air alone in the annular gap
 
Creator BOPCHE, SB
SRIDHARAN, A
 
Subject pebble bed reactors
natural-convection
surface radiation
droplet flow
bundles
core
coolant
water
circulation
design
radiation
decay-heat-removal
single rod
fuel bundle
nuclear
experimental
 
Description During a loss of coolant accident in nuclear reactors, radiation heat transfer accounts for a significant amount of the total heat transfer in the fuel bundle. In case of heavy water moderator nuclear reactors, the decay heat of a fuel bundle enclosed in the pressure tube and outer concentric calandria tube can be transferred to the moderator. Radiation heat transfer plays a significant role in removal of decay heat from the fuel rods to the moderator, which is available outside the calandria tube. A single heater rod test facility is designed and fabricated as a part of preliminary investigations. The objective is to anticipate the capability of moderator to remove decay heat, from the reactor core, generated after shut down. The present paper focuses mainly on the role of moderator in removal of decay heat, for situation with air alone in the annular gap of pressure tube and calandria tube. It is seen that the naturally aspirated air is capable of removing the heat generated in the system compared to the standstill air or stagnant water situations. It is also seen that the flowing moderator is capable of removing a greater fraction of heat generated by the heater rod compared to a stagnant pool of boiling moderator.
 
Publisher ELSEVIER SCIENCE INC
 
Date 2011-07-27T08:47:12Z
2011-12-26T12:56:28Z
2011-12-27T05:45:16Z
2011-07-27T08:47:12Z
2011-12-26T12:56:28Z
2011-12-27T05:45:16Z
2010
 
Type Article
 
Identifier EXPERIMENTAL THERMAL AND FLUID SCIENCE, 34(8), 1456-1474
0894-1777
http://dx.doi.org/10.1016/j.expthermflusci.2010.07.009
http://dspace.library.iitb.ac.in/xmlui/handle/10054/7173
http://hdl.handle.net/10054/7173
 
Language en