nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
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Criticality Safety Section 3<br />
The fission product exhibiting the most rapid in<strong>cr</strong>ease with burnup is the stable nuclide 155 Gd. Its precursor<br />
155 Eu has a 4.75-year half-life, and so 155 Gd has not reached equilibrium even for a 70-GWd/t exposure. The<br />
importance of 155 Gd in<strong>cr</strong>eases by an order of magnitude between 20 and 60 GWd/t for cooling times greater<br />
than about 5 years, and it is one of the larger fission-product absorbers in high-burnup fuel. Another stable<br />
nuclide, 153 Eu, exhibits a similar, although less-pronounced effect, as its precursor 153 Gd and has a 241.6-day<br />
half-life. However, 153 Eu ranks considerably lower than 155 Gd in high-burnup fuel for cooling times more<br />
than 5 years.<br />
The <strong>cr</strong>iticality safety nuclide rankings were recomputed for the PWR fuel using a SAS2 model in which the<br />
specific power was 25 MW/t. In general, the nuclide rankings were not affected, except that (rarely) the<br />
order of two nuclides could be reversed. In those cases, the absorption rates for the nuclides whose order<br />
changed were essentially identical. The only noticeable difference in the actinides for decay times from 5 to<br />
100 years was an in<strong>cr</strong>ease of about 6% in the absorption fraction for 238 Pu. The amount of 238 Pu in<strong>cr</strong>eases<br />
because its precursor 237 U (produced both by capture from 235 U to 236 U and from (n,2n) from 238 U) undergoes<br />
relatively more decays to 237 Np when the power (and therefore flux) is lower. The biggest changes in<br />
fission-product absorption rates were for the stable 149 Sm (−11%) and 157 Gd (−15%) nuclides that have large<br />
capture <strong>cr</strong>oss sections.<br />
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