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ORNL-1816 - the Molten Salt Energy Technologies Web Site

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PERIOD ENDING DECEMBER 70,7954<br />

TABLE 13.1. NUMERICAL VALUES OF TERMS IN REMOVAL-CROSS-SECTION CALCULATIONS<br />

Term<br />

Value in<br />

Bismuth<br />

Value in Value in<br />

Lithium Stainless Steel<br />

t, cm 22.86 27.23 1.91 (total)<br />

127.1<br />

150<br />

7.20 x lo-'<br />

6.20 X loe2<br />

120.9<br />

150<br />

1.44 x loo<br />

2.30 X lo-'<br />

9.17<br />

9.00<br />

9.90<br />

10.1<br />

9.54<br />

9.55<br />

35.56<br />

35.56<br />

9.80<br />

0.53 7.8<br />

0.603 x<br />

0.603 x 0.603 x lo2*'<br />

M, atomic mass 20 9 6.94 55.85<br />

Long) in Raschig Ring-Borated Water Medium;<br />

z = 136 cm.<br />

REFLECTOR-MODERATED REACTOR AND<br />

SHIELD MOCKUP TESTS<br />

J. B. Dee<br />

It was previously reported2 that <strong>the</strong> radiation<br />

decomposition in samples of a solution of UF,<br />

in C,F, was found to be too great for use of <strong>the</strong><br />

liquid as <strong>the</strong> simulated fuel in <strong>the</strong> LTSF inockups<br />

of <strong>the</strong> circulating-fuel reflector-moderated reactor.<br />

It is now planned to use solid UO, in <strong>the</strong> form of<br />

enriched uran i um-a1 umi nu m MTR-type fuel plates.<br />

under operating conditions in a special rig outside<br />

<strong>the</strong> LTSF. O<strong>the</strong>r preparations for <strong>the</strong> tests are<br />

being completed.

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