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Development and Verification of Nuclear Calculation Methods for ...

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- 41 -<br />

ly with a detailed spatial isotopic depletion.<br />

The programme can be provided with multi-group microscopic cross<br />

sections in either card or magnetic tape <strong>for</strong>m.<br />

Accumulated burn-up, space-dependent flux spectra <strong>and</strong> number densities<br />

as well as reactivity <strong>and</strong> homogenized few-group macroscopic cross<br />

sections <strong>for</strong> later application in, <strong>for</strong> example, diffusion theory, are printed<br />

<strong>for</strong> each time step.<br />

The CEB programme is written in the ILLINOIS-ALGOL language with<br />

dynamic overlay <strong>and</strong> with link structure shown in fig. 5.<br />

<strong>Verification</strong> <strong>of</strong> the programme will be given in section 10, where cell<br />

burn-up calculations <strong>for</strong> the Yankee reactor (ref. 20 ) will be compared<br />

with calculations per<strong>for</strong>med with LASER as well as with experimental data.<br />

With 16 group microscopic cross sections from the LASER-CROSS<br />

MICRO complex, a typical Yankee unit cell burn-up calculation requires<br />

about 3 sec per time step.<br />

A detailed spatial fission product depletion was recently incorporated<br />

in the CEB programme (ref. 29). The FIPO procedure accounts <strong>for</strong> 166 different<br />

isotopes distributed on 68 linear chains by means <strong>of</strong> a combined<br />

analytical <strong>and</strong> numerical method without any further serious computational<br />

ef<strong>for</strong>ts.

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