In-Pile Test of Prototype ML-1 Fuel Elements Page: 24
xvi, 189, [12] p. : ill. ; 28 cm.View a full description of this report.
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Report No. IDO-28616
TABLE 7-2 - IB-8T TEMPERATURE INSTRUMENTATION
THERMOCOUPLE
Test Element Function No. and Position Sheath Diameter*, in.
IB-8T-1 & -3 Gas Coolant 2 Inlet 0.060
4 Outlet 0.060
Fuel Central 1 Pellet 0.040
Pellet Core
Cladding 7 Axial & 0.040
Radial
IB-8T-2 Gas Coolant 2 Inlet 0.060
4 Outlet 0.060
*Inconel tube
thermocouples terminated in stainless steel discs which provided a heat path
from the interior of the cladding to the thermocouple junction. The discs
were insulated from the fuel pellet on either side with zirconia wafers. The
fuel pellets in this element were cored (0.050-in. dia) to accommodate the
thermocouples for cladding and fuel temperature sensing. The thermocouple
sheaths were brazed to the Hastelloy X upper plug, and the leads were spliced
to Inconel-sheathed chromel/alumel thermocouple extensions immediately above
the element. Figure 7-3 shows the arrangement of the cladding and fuel thermo-
couples in the fuel pins.
The IB-8T-2 (uninstrumented) element was not equipped with thermocouples
in the fueled region but was equipped with four thermocouples to sense outlet
gas temperatures and two to sense inlet gas temperatures.
7.2 Dunmmy Elements
Two dummy elements were fabricated for use in non-nuclear tests of the
loop. The elements, identical except that one was instrumented, included in-
sulated liner assemblies identical with those described for the IB-8T test ele-
ments. The fuel pin bundle was omitted from the dummy elements and an orifice
(0.650-in. ID) was installed to approximate the pressure drop of the pin bundle
at reference flow conditions. One dummy element was equipped with thermocouples
to sense coolant gas temperature at the inlet and outlet of the element and the
outer liner temperature.
7.3 Flux Measuring Element
The flux measuring element was a 19-pin bundle equipped with a 6-in.
long fuel stack, and inserted into the liner assembly so that the center plane
of the flux element coincided with the center plane of the GETR. A spring
spacer held the fuel pin bundle in the flux element and facilitated disassembly
for counting after irradiation (Fig. 7-4). The probe and bracket on the lower
end of the assembly anchored the flux element in the GETR pool, duplicating the
location of the test elements. Cored fuel pellets, identical with those used24
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Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W. In-Pile Test of Prototype ML-1 Fuel Elements, report, June 1964; San Ramon, California. (https://digital.library.unt.edu/ark:/67531/metadc100224/m1/40/: accessed April 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.