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Development and Verification of Nuclear Calculation Methods for ...

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2. THE TWODIM SYSTEM OF PROGRAMMES FOR NUCLEAR<br />

LIGHT-WATER REACTOR CALCULATIONS<br />

The TWODIM SYSTEM <strong>of</strong> programmes <strong>for</strong> nuclear light-water reactor<br />

calculations is shown in fig. 1 where also the magnetic tape file transfer <strong>of</strong><br />

data between the programmes is indicated. The system covers a wide range<br />

<strong>of</strong> nuclear light-water reactor calculation methods from the unit cell to the<br />

assembly <strong>and</strong> the over-all reactor treatments. Integral transport theory<br />

<strong>and</strong> diffusion theory are applied <strong>for</strong> the stationary flux solution, <strong>and</strong> the<br />

time-dependent irradiation is followed in the quasistationary approach by<br />

means <strong>of</strong> various burn-up methods.<br />

The transfer <strong>of</strong> data is normally from programmes with many groups<br />

<strong>and</strong> poor spatial dissolution to programmes with fewer groups <strong>and</strong> better<br />

spatial dissolution.<br />

It originates in the LASER unit cell burn-up programme that was used<br />

as the primary source <strong>of</strong> nuclear cross section data throughout the project<br />

on account <strong>of</strong> the built-in multi-group cross section libraries. The CROSS<br />

MACRO dsta prcccsGing pi'ugx-amme may provide macroscopic <strong>and</strong> homogenized<br />

cross sections <strong>for</strong> direct application in over-all reactor calculations<br />

with the two-dimensional diffusion equation programmes TWODIM <strong>for</strong><br />

the stationary flux solution <strong>and</strong> DBU ana CDB <strong>for</strong> time-dependent burn-up<br />

investigations. The CELL cross section condensation programme <strong>and</strong> the<br />

HECS gamma-matrix calculation Drogramme determine equivalent cross<br />

sections <strong>and</strong> boundary conditions <strong>for</strong> proper representation <strong>of</strong> <strong>for</strong> example<br />

control regions in over-all diffusion theory calculations respectively. The<br />

CROSS MICRO data processing programme provides microscopic cross<br />

section libraries <strong>for</strong> the fast unit cell burn-up programme CEB <strong>and</strong> <strong>for</strong> the<br />

treatment <strong>of</strong> the individual fuel rods in the combined unit cell <strong>and</strong> over-all<br />

reactor CDB programme.<br />

The overlay structures <strong>of</strong> the various programmes are shown in figs. 2<br />

through 8, <strong>and</strong> the functions <strong>of</strong> the indicated subroutines <strong>and</strong> procedures are<br />

explained in the appendix.<br />

The fundamental physical <strong>and</strong> mathematical methods developed <strong>and</strong><br />

employed in these programmes <strong>and</strong> the associated physical consequences<br />

are now described <strong>and</strong> discussed in the subsequent sections.

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