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JAEA-Data/Code 2007-004 - Welcome to Research Group for ...

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i<br />

n m≠n<br />

i<br />

n<br />

i<br />

n<br />

i<br />

n<br />

i 1<br />

i i g(<br />

C )(1 − C )<br />

σ<br />

0, n<br />

= ∑(<br />

N<br />

mσ<br />

t,<br />

m<br />

) +<br />

(1.6-2)<br />

i<br />

N<br />

N L<br />

i a<br />

g(<br />

Cn<br />

) = (1.6-3)<br />

1 + ( a −1)<br />

C<br />

i<br />

n<br />

where N is the a<strong>to</strong>mic number density, L the mean chord length, C n the nuclide dependent Dancoff<br />

correction fac<strong>to</strong>r 19) and a the Bell fac<strong>to</strong>r defined in the SRAC code by the geometry of absorbing<br />

mixture.<br />

The nuclide dependent Dancoff fac<strong>to</strong>r is specified optionally by the input value or the calculated<br />

value assuming the black limit in case that the collision probability method is used. The nuclide<br />

dependence of Dancoff fac<strong>to</strong>r is effective <strong>for</strong> the lattice including two or more different kinds of<br />

resonant mixtures.<br />

The infinite dilution cross-sections are given <strong>to</strong> the nuclide which has no f-table or <strong>to</strong> every<br />

nuclide of the energy group out of range of tabulation. Current available libraries of SRAC have<br />

f-tables <strong>for</strong> all resonant nuclides as far as resonance levels are evaluated in nuclear data file. f-table is<br />

given <strong>for</strong> the reactions capture, fission, <strong>to</strong>tal, elastic, and elastic removal in the fast energy range, and<br />

reactions capture, fission and <strong>to</strong>tal in the thermal energy range.<br />

Dancoff correction by Tone’s method 20) is also available. In this method, the background<br />

cross-section is calculated by the following <strong>for</strong>mula;<br />

∑∑<br />

j j<br />

N m Pj→iσ<br />

t,<br />

m<br />

j m≠n<br />

i<br />

σ 0, n =<br />

, (1.6-4)<br />

j j<br />

N P V<br />

∑<br />

j<br />

n<br />

j→i<br />

where collision probability from region j <strong>to</strong> region i,<br />

Pj<br />

→ i<br />

V<br />

j<br />

V j volume of region j.<br />

The cell heterogeneity is evaluated so as <strong>to</strong> consider contributions from each region in a unit fuel cell<br />

through collision probabilities. This method is expected <strong>to</strong> be effective <strong>for</strong> plate type fuel cell, where a<br />

resonant nuclides exists in several composite mixtures with different number densities. It should not be<br />

used <strong>for</strong> a normal pin type fuel cell.<br />

1.6.2 IR Approximation<br />

This method can be applied <strong>to</strong> the problem where a cell has only one resonant mixture (i=1<br />

only). The microscopic effective resonance cross-sections are given by Eq.(1.6-5) by the interpolation<br />

of f-table as well as the NR approximation.<br />

13

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