Recommendations for modeling upper plenum injection system for a pressurized water reactor
Name
MIT-EL-78-031-04842804.pdf
Size
1.89 MB
Format
Adobe PDF
Checksum (MD5)
a3466fd1111b4134a8d7c0f0065bdbe0
Author(s)
Griffith, Peter
Kan, John
Date Issued
October 1978
Publisher
MIT Energy Laboratory
Series/Report no.
MIT-EL
78-031
Abstract
The present work examines the unique heat transfer modeling
problems associated with analysis of performance of an upper plenum
emergency core cooling injection system during a postulated
Loss-of-Coolant Accident (LOCA) in a pressurized water reactor.
The particular system under study consists of four 4-inch pipes
conveying emergency core cooling water from outside the pressure vessel
through four spare control and rod mechanism housings and internal
pipings, discharging the water directly over the top of the reactor
core.
Previously, it has been assumed that the water injected into the
upper plenum passes through the reactor core to the lower plenum
without any heat interaction with the fuel rods during a LOCA. This
simplified model neglects the many beneficial and adverse effects that
accompany the upper plenum injection.
This study is undertaken to examine the following items
· heat transfer to the emergency core coolant before reaching
the core
· flow and heat transfer through the reactor core
· reflood heat transfer.
The phenomena occurring will be delineated and recommendations
made for calculating both conservative and best estimate values. The
method of solving these problems will be illustrated in a series of
examples given in the appendices.
Subjects
Nuclear fuel elements.
Pressurized water reactors |x Cooling.
Pressurized water reactors |x Safety measures.
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