IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
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IGC<br />
<strong>Annual</strong> <strong>Report</strong> 2007<br />
III.A.5. Investigation of Thermal Striping at the<br />
Bottom of the Control Plug<br />
When non-isothermal fluid<br />
streams mix adjacent to a<br />
structure, the surface of the<br />
structure experiences<br />
temperature fluctuations and<br />
can develop cracks due to<br />
thermal fatigue. This<br />
phenomenon is called thermal<br />
striping. In fast breeder<br />
reactors, the coolant coming<br />
out from the fuel subassemblies<br />
is hotter than the coolant<br />
coming out of the blanket and<br />
absorber rod subassemblies.<br />
The improper mixing of the jets<br />
issuing out from these<br />
subassemblies results in<br />
temperature fluctuations in the<br />
fluid. This may lead to the<br />
structural damage of control<br />
plug components like shroud<br />
tubes, lattice plate, skirt etc.<br />
An experiment has been<br />
carried out in SAMRAT model to<br />
understand the mixing<br />
behaviour and to determine the<br />
extent of thermal striping in the<br />
above core area of PFBR.<br />
SAMRAT is a 1/4 scale model<br />
of PFBR primary circuit. Demineralized<br />
water is used as<br />
simulant in this model.<br />
It has been established by the<br />
earlier researchers that air or<br />
water can be used to simulate<br />
thermal striping phenomenon<br />
in sodium if Reynolds (Re)<br />
number and Peclet (Pe) number<br />
are sufficiently large (Re ><br />
20,000 and Pe > 600) both in<br />
prototype and model. The fluid<br />
thermal fluctuations as<br />
measured using the simulant<br />
fluid, can be transposed to the<br />
prototype condition if<br />
temperature is measured<br />
outside the thermal boundary<br />
layer. The attenuation of<br />
temperature fluctuations within<br />
the boundary layer can be<br />
determined accurately using<br />
sodium experiments.<br />
In the present work mixing in<br />
the fuel-blanket interface<br />
region was studied. Hot water<br />
at 343 K was sent through the<br />
fuel zone and cold water at 308<br />
K was sent through blanket<br />
zone. To measure the fluid<br />
thermal fluctuations, fast<br />
response thermocouples (time<br />
constant better than 15 ms)<br />
were used.<br />
Temperature (C)<br />
70<br />
60<br />
50<br />
40<br />
30<br />
20<br />
Temperature_mixing zone<br />
Temperature_cold water<br />
Temperature_hot water<br />
0 2 4 6 8 10<br />
Time<br />
Fig.1 Time series plot of temperature<br />
at mixing region<br />
Fig.1 shows a typical time series<br />
plot of the temperature as<br />
measured in the mixing zone.<br />
From the statistical analysis of<br />
data the mean temperature as<br />
seen by each thermocouple was<br />
estimated. These temperature<br />
data are presented in a<br />
normalized <strong>for</strong>m to transpose<br />
the result into reactor case by<br />
substituting the prototype<br />
parameters. The normalization<br />
is done in the following<br />
manner.<br />
where,<br />
T = Mean temperature<br />
of the fluid as measured by the<br />
thermocouple mounted in CP<br />
T h = Mean temperature<br />
of the hot inlet fluid<br />
(Thermocouple mounted at the<br />
SA exit)<br />
T c = Mean temperature<br />
of the cold inlet fluid<br />
(Thermocouple mounted at the<br />
SA exit)<br />
∆Trms = Root mean<br />
square of temperature<br />
fluctuations.<br />
32 R&D FOR FBRs