ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory ORNL-1771 - Oak Ridge National Laboratory
with and without 0.OZin.-thick cadmium covers. The data obtained along a radius 36.7 cm from the bottom of the core and somewhat removed from the high-solution-density perturbation are shown in Fig. 4.5. Similar data from a longitudinal traverse located 2.4 cm from the cylinder axis are given in Fig. 4.6. Although these results are preliminary, it is believed that the apparent nonuniformity of the radial thermal flux is greater fhan the experi- mental uncertainty. A few measures show the radial importance of U23s to also decrease from the center. In one experiment to evaluate the Furfural re- flector, annular sheets of aluminum were inserted adjacent to the wall of the reactor tank, thereby reducing the reflector thickness from 10.0 cm to 3.6 cm. The effect of the aluminum, indicated by the critical height of the Furfural, was o slight increase in the reactivity. PERIOD ENDING SEPTEMBER 70, 1954 TABLE 4.2 CONFIGURATION OF SCWR CRITICAL EXPERIMENT Experimental Design Number of tubes" 215.0 215.0 Height of U02F2 solution, cm 71.2 76.2 Height of Furfural, cm 69.5 76.2 Mass of U235, kg** 11.48 15.34 Thickness of reflector, cm 10.0 6.5 Mass of stainless steel, kg 220.4 261.0 *Expressed as equivalent number of tubes 1 in. in diameter; the array contains 193 which are 1 in. in diameter, 8 which are 3 . /4 in., and 25 which are !$ in. **Of this loading, 86.8% was in a solution having a U235 concentration of 0.196 g/cm 3 , and 13.2% wus in one with a U235 concentration of 0.505 g/cm 3 . slc ORNL--LR--0WG 302C Fig. 4.5. Radial Neutron Distribution in Supercritical-Water Reactor Critical Assembly. 49
78 26 24 22 20 IE t 2 ('0 t- u 14 w 2 t- 5 12 K w IO 50 8 6 4 2 + -- J - + - - - I __ .................. ~ ........... 1- 1 INDILM ACTIVATION MINUS CADMIUM - COVERED INDIUM ACTIVATION ' I ~i -.-.-. ~~ 1 DISTANCE FROhl REACTOR TANK FLOOR (cm) L~~ ' fig. 4,Q. Longitudinal Neutron Distribution in Supercritical-Water Reactor Critical Assembly. ORNL-LR -D'.VG 302< -- I - - 10 09 0.8 0.7 L 06 ? 0 a 0.5 2 3 345 n 03 32 3.1 0
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