ORNL-2106 - the Molten Salt Energy Technologies Web Site
ORNL-2106 - the Molten Salt Energy Technologies Web Site
ORNL-2106 - the Molten Salt Energy Technologies Web Site
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0 20 40 60 80 lo0 I20 440 (60 180 200 220<br />
DISTANCE ALONG LOOP FROM INLET TO COOLED SECTION (cm 1<br />
Fig. 4.2.13. Plot of Glculated Temperature<br />
Differential Through <strong>the</strong> Fuel Tube Wall as a<br />
Function of <strong>the</strong> Distance from <strong>the</strong> Fuel Inlet of<br />
LITR Vertical In-Pile Loop.<br />
FURTHER DESIGN CALCULATIONS FOR<br />
LITR VERTICAL IN-PILE LOOP<br />
M. T, Robinson<br />
ark Vlll loop described<br />
"4 T. Robinson, Solid State Semiann. Prog. Rep.<br />
Feb. 28, 1954, <strong>ORNL</strong>-1677, p 27.<br />
PERIOD ENDING JUNE 10. 1956<br />
flection of <strong>the</strong> measured flux in <strong>the</strong> plane of its<br />
maximum value. The computations were carried<br />
out on <strong>the</strong> Reactor Controls Computer according<br />
to <strong>the</strong> technique previously described,'* except<br />
that <strong>the</strong> flux function was generated electronically<br />
instead of mechanically.<br />
Calculations were made for <strong>the</strong> fuel mixture<br />
(No. 44) NaF-ZrF4-UF, (53.5-40-6.5 mole %) con-<br />
tained in Inconel in <strong>the</strong> new position and for <strong>the</strong><br />
fuel mixture (No. 107) NaF-KF-LiF-UF4 (11.2-<br />
41-45.3-2.5 mole %) contained in Hastelloy B in<br />
both positions. The Fhysical property data used<br />
for air, for Inconel, and for <strong>the</strong> zirconium-bearing<br />
fuel mixture were <strong>the</strong> same as those used previ-<br />
ously. The data for <strong>the</strong> alkali-metal fuel and<br />
Hasteltoy B are given below:<br />
Density of fuel,17 g/cm3 2.09<br />
Specific heat of w*~ec/g*~C 2.28<br />
Viscosity of fuel,19 g/crn-sec 0.022<br />
Thermal conductivity of fuel, 20<br />
w/cm*OC<br />
0.035<br />
Thermal conductivity of Hastelloy BI2' 0.1 13<br />
w/cm*OC<br />
As before, <strong>the</strong> depression of <strong>the</strong> <strong>the</strong>rmal-neutron<br />
flux because of <strong>the</strong> presence of <strong>the</strong> loop was<br />
neglected.<br />
The results of <strong>the</strong> calculations are summarized<br />
in Table 4.2.1. It is shown that, in spite of <strong>the</strong><br />
greater length of <strong>the</strong> irradiated loop in <strong>the</strong> "deep"<br />
position, <strong>the</strong> fuel temperature differential is less<br />
than that in <strong>the</strong> position of maximum flux. The<br />
principal result of <strong>the</strong> change in position of <strong>the</strong><br />
loop is a substantial decrease in <strong>the</strong> dilution<br />
16E. R. Mann, F. P. Green and R. S. Stone, "An<br />
Appendix on Analog Simulation," in Design Calculations<br />
for a Miniature Higb-Temperature In-Pile Circulating<br />
Fuel Loop, by M. T. Robinson and D. F. Weekeg,<br />
OWL-1808 (Sept. 19, 1955).<br />
stimated by method of S. 1. Cohen and T. N.<br />
, A Summary of Density Measurements on <strong>Molten</strong><br />
Fluoride Mixtures and a Correlation Useful for Predicting<br />
Densities of Fluoride Mixtures 01 Known<br />
Compositions, <strong>ORNL</strong>-1702 (May 14, 1954).<br />
18Estimated on assumption that <strong>the</strong> alkali-metal fuel<br />
s <strong>the</strong> same molar heat capacity as that of <strong>the</strong> zirconium-bearing<br />
fuel.<br />
19S. 1. Cohen, personal communications to M. T.<br />
Robinson, March 16, 1956, and May 4, 1956.<br />
"Estimated by W. D. Powers, March 16, 1956.<br />
21 Haynes Stellite Company, Hastelloy Highstrength,<br />
Nickel-Base, Corrosion-Resistant Alloys, p 15, Sept. 1,<br />
1951.<br />
241