ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
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with unirradiated iron that had entered <strong>the</strong> fuel<br />
during or after opening of <strong>the</strong> lnconel capsule. The<br />
techniques developed by G. Smith (Analytical<br />
Chemistry Division) are particularly adaptable to<br />
<strong>the</strong> separation of minute amounts of iron (10 to 100<br />
pg) from very large amounts of fission products.<br />
Four samples of fuel from irradiated capsules<br />
showed that between 70 and 99% of <strong>the</strong> iron came<br />
from an unirradiated source, whereas samples from<br />
an irradiated lnconel capsule showed that less than<br />
6% of its iron content was not radioactive. Since<br />
<strong>the</strong> amount of iron contamination involved is very<br />
small (of <strong>the</strong> order of 50 pg), some possible sources<br />
of contamination would include <strong>the</strong> steel drill used<br />
to remove <strong>the</strong> fuel from <strong>the</strong> capsules and also <strong>the</strong><br />
impurities in <strong>the</strong> reagents used in preparing sample<br />
solutions. In <strong>the</strong> future, samples will be obtained<br />
by using a nonferrous drill. Unfortunately, radio-<br />
activation techniques cannot be applied to analyses<br />
for chromium and nickel because of unfavorable<br />
activation yields, insensitivity of detection, and<br />
chemical separation difficulties associated with<br />
trace amounts of <strong>the</strong>se elements.<br />
An improved and modified version of <strong>the</strong> capsule<br />
irradiation facility is being put into service (Fig.<br />
9.1). Before being shipped from <strong>ORNL</strong>, each<br />
capsule is mounted in a sleeve which provides a<br />
sufficiently large annulus for <strong>the</strong> passage of cooling<br />
air between it and <strong>the</strong> capsule. The bottom of <strong>the</strong><br />
INSTALLATION OF IRRADIATION TUBES<br />
IN MTR REFLECTOR 'r PIECE<br />
AIR PATH<br />
YPICAL THERMOCOUPL<br />
PERIOD ENDING DECEMBER 70,1954<br />
sleeve is tapered to fit an inside taper at <strong>the</strong><br />
bottom of <strong>the</strong> air tube in <strong>the</strong> MTR. The advantage<br />
of this arrangement is that <strong>the</strong> capsule can be<br />
fitted to <strong>the</strong> sleeve prior to insertion into <strong>the</strong><br />
reactor. Several tubes and capsules prepared with<br />
this new arrangement have been used satisFactorily<br />
in <strong>the</strong> MTR. In order to speed up <strong>the</strong> capsule<br />
program, arrangements have been made for irradiating<br />
two capsules simultaneously in separate, but<br />
adiacent, facilities in <strong>the</strong> MTR.<br />
An improved set of temperature controls fabricated<br />
by <strong>the</strong> Instrumentation and Controls Division has<br />
been subjected to dynamic performance tests by<br />
using an electrically heated capsule. These tests<br />
have shown that <strong>the</strong> new controls will maintain a<br />
more constant temperature in <strong>the</strong> capsule during<br />
irradiation.<br />
EFFECT OF IRRADIATION ON UF,-C,F,,<br />
W. E. Browning G. W. Keilholtz<br />
Solid State Division<br />
Examinations were made of material from welded<br />
nickel capsules that were filled under vactmm with<br />
a UF,-C,F,, solution containing 20 wt % IJF, and<br />
<strong>the</strong>n irradiated in <strong>the</strong> <strong>ORNL</strong> Graphite Reactor and<br />
in <strong>the</strong> Tower Shielding Facility. These irradiations<br />
were made to determine <strong>the</strong> suitability of UF,-<br />
C,F,, for use as fuel in a Lid Tank Shielding<br />
Facility mockup of <strong>the</strong> circulating-fuel reactor.<br />
IRRADIATION TUBE WITH CAPSULE INSTALLED<br />
rANNULUS SLEEVE<br />
IRRADIATION TUBE WITH CAPSULE REMOVED<br />
Fig. 9.1. New Apparatus for insertion of Capsules in <strong>the</strong> MTR.<br />
-9<br />
<strong>ORNL</strong>-LR-DWG 4603<br />
121