26.10.2014 Views

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

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

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

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

Formerly the PEACO worked only in the second resonance energy range. Now, the upper energy limit<br />

can be extended up <strong>to</strong> 961.12eV optionally.<br />

1.5.5 Thermal Neutron Energy Range (cut-off-energy > E > 1.0E-5eV)<br />

The cut-off-energy should be determined by considering the effect of up-scattering, resonance<br />

levels around the cut-off-energy and the continuity of scattering cross-sections described at the<br />

previous section. Judging from the comparisons with continuous energy Monte Carlo calculation<br />

results, about 2.0eV is recommended, even if sharp resonance levels lower than this energy can not be<br />

treated by the PEACO option. The Maxwellian distribution depending on temperature and 1/E is<br />

assumed <strong>for</strong> the asymp<strong>to</strong>tic spectrum.<br />

1.6 Effective Resonance Cross-sections<br />

The SRAC code installs three kinds of methods <strong>for</strong> calculation of effective resonance<br />

cross-sections, they are, NR approximation, IR approximation and the PEACO calculation. One of<br />

them is selected by the characteristics of the problem, the required accuracy or computation cost. The<br />

NR approximation is defaulted unconditionally. If one of other options is specified, the cross-sections<br />

obtained by the NR approximation are replaced by the values calculated by the IR or the PEACO<br />

calculation, in the energy range where each option is active.<br />

1.6.1 NR Approximation<br />

The Fast and Thermal Libraries contain the infinite dilution cross-sections ( σ ) of every<br />

nuclide and the tabulation of self-shielding fac<strong>to</strong>rs <strong>for</strong> resonant nuclides (f-table). The effective<br />

microscopic cross-section of reaction x of nuclide n in resonant mixture i is given by Eq.(1.6-1) using<br />

the above quantities.<br />

∞<br />

σ<br />

i<br />

x,<br />

n<br />

= σ<br />

∞,<br />

x,<br />

n<br />

f<br />

i<br />

x ( σ 0,<br />

n<br />

, T<br />

i<br />

)<br />

(1.6-1)<br />

i i<br />

where f x ( σ 0,<br />

n , T ) is the resonance self-shielding fac<strong>to</strong>r obtained by the interpolation of the f-table<br />

i<br />

with a parameter: background cross-section σ 0,n defined by Eq.(1.6-2) and another parameter: the<br />

i<br />

temperature T of the mixture of which the nuclide is a constituent. The interpolation is carried out<br />

by using the third order spline function. The background cross-section is given by the equivalence<br />

theory between homogeneous system and heterogeneous system as<br />

12

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!