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

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63<br />

n e results of a program of solution <strong>the</strong>modynamics,25926 a ~ong-tem<br />

program of in-pile irradiations,5’ atad a number of special experiments<br />

gemmed genel~aiiy accurate preaietions, 63-65 but much of our detailed -<br />

and still incomplete - understanding of fission-product behavior comes<br />

from operation of <strong>the</strong> ~ ~ 1 ~ ~ me ~ ~ ability 9 2 of 2 <strong>the</strong> ~ fissfsn ~ 2 produets<br />

to form stable compounds and to dissolve in <strong>the</strong> molten fuel serves to<br />

divide <strong>the</strong>m into <strong>the</strong> three distinct groups described in <strong>the</strong> following<br />

dissussisn.<br />

e . Krypton and xenon (which<br />

is an important neutron absorber) fom no eorrapounds under conditions ex-<br />

isting in a DMSR or o<strong>the</strong>r molten-salt reactor.19,73 Noreover, <strong>the</strong>se<br />

gases are only very sparingly soluble in molten fluoride mixtures. 74-76<br />

As with all noble gases (see Fig. la), 76 <strong>the</strong>ir solubility increases with<br />

temperature and with diminishfng size of <strong>the</strong> gaseous atom, while <strong>the</strong> heat<br />

of solution increases with increasing atomic size. This low solubility<br />

is a distinct advantage because it enables <strong>the</strong> ready removal sf krypton<br />

and xenon from <strong>the</strong> reactor by sparging with helium.<br />

The relatively sim-<br />

ple sparging system of <strong>the</strong> MSRE served to remove more than 80% of <strong>the</strong><br />

13%e, and far more efficient spargbng was proposed for <strong>the</strong> MSBR.”<br />

Stripping of <strong>the</strong> noble gases from <strong>the</strong> reactor after a short residence<br />

time avoids <strong>the</strong> presence of <strong>the</strong>ir radioactfve daughters in <strong>the</strong> fuel.<br />

Tritium qualifies as a fission product because mall quantities of<br />

it are produced in ternary fissions. However, essentially all of <strong>the</strong><br />

tritium anticipated in MSBR’Q,~~ results from o<strong>the</strong>r sources, as shown in<br />

Table 27.<br />

A DMSW at similar power level and with a generally similar fuel must<br />

be expected to generate tritium at approximately this same rate. This<br />

tritium will originate in principle as 3 ~ however, ~ ; with appreciable<br />

esneentrations of ~3 present, this ’HF will be reduced largely to %2.<br />

A However, note that <strong>the</strong> pores in <strong>the</strong> moderator graphite can offer a<br />

haven far &heSE? gases.

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