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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

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