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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

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