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ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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E<br />

6><br />

I S<br />

N<br />

0.45<br />

k- 0.50 B --.<br />

8.25<br />

BWNL-DWG 804264 ETB<br />

I I<br />

0.80 0.85 0.98 0.95 1.00<br />

ROD DIAMETERPITCH RATIO<br />

Fig. 3. Mean chord length of fuel surrounding triangular arrays<br />

of moderator rods. Circles illustrate predictions by <strong>the</strong> 48lA rule.<br />

<strong>the</strong> results of this treatment. 'Phe salt in <strong>the</strong> plenum and radial gap re-<br />

gions was represented as a 0.05-m plane environment.<br />

The resulting multigroup cross sections were used with <strong>the</strong> XSDRMPM<br />

module of AMPX to accomplish a discrete-ordinates cell calculation in<br />

<strong>the</strong> S-4 approximation and to accomplish group reduction to three energy<br />

groups, as shorn in Table 6. A separate cell calculation was performed<br />

for each of <strong>the</strong> two log diameters. Plenum and gap C~QSS sections were<br />

weighted over <strong>the</strong> spectrum of <strong>the</strong> smaller log diameter because it lies<br />

between <strong>the</strong> standard diameter and <strong>the</strong> pure salt region in hardness.<br />

The basic concentrations sf <strong>the</strong> nuclides were based on estimated<br />

midlife conditions. Additional cases of self-shielding for <strong>the</strong> thorium

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