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

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If a group-dependent <strong>for</strong>m of Fick’s law is postulated, i.e.,<br />

J<br />

( r)<br />

= − ( r)<br />

∇Φ<br />

( r)<br />

g D g<br />

g<br />

(7.2-5)<br />

then from Eq.(7.2-4) the diffusion coefficient can be <strong>for</strong>mally expressed by<br />

with<br />

D g<br />

Σ<br />

1<br />

( r)<br />

= (7.2-6)<br />

3Σ<br />

( )<br />

( r)<br />

≡ Σ<br />

tr, g r<br />

−<br />

Σ<br />

tr, g t,<br />

g ∑ s1,<br />

g ' →g<br />

J g ' g r<br />

g '<br />

( r) / J ( )<br />

(7.2-7)<br />

If the group width is wider compared with the maximum energy degradation of neutron by<br />

elastic collision and the quantity EJ(r, E) can be assumed <strong>to</strong> be energy-independent in the width, we<br />

can show 52)<br />

∑<br />

g '<br />

Σ<br />

in this case, we have<br />

∑<br />

( r ) / J ( r)<br />

≅ Σ = ( μ Σ<br />

(7.2-8)<br />

s1 , g ' →g<br />

J g ' g<br />

s1,<br />

g→g'<br />

) g<br />

g'<br />

s,<br />

g<br />

Σ<br />

tr, g ( r)<br />

= Σ<br />

t,<br />

g<br />

−<br />

∑<br />

g '<br />

Σ<br />

s1,<br />

g→g'<br />

(7.2-9)<br />

Four methods are prepared <strong>to</strong> define the transport cross-section <strong>to</strong> be used as <strong>to</strong>tal cross-sections<br />

in the isotropic transport calculation or diffusion calculation.<br />

(1) Optional Process IC16 = 0<br />

The first one treats simply the anisotropic scattering effect in the isotropic transport calculation<br />

by the extended transport approximation 23) . Here, the macroscopic transport cross-section is defined<br />

by<br />

Σ<br />

tr,<br />

g<br />

= Σ<br />

t,<br />

g<br />

−<br />

∑<br />

g'<br />

Σ<br />

s1,<br />

g→g'<br />

(7.2-10)<br />

It should be noted that the <strong>to</strong>tal cross-section, instead of the transport cross-section, is used <strong>to</strong><br />

calculate the collision probability in the second resonance range, where the ultra-fine spectrum is<br />

calculated by assuming isotropic neutron scattering.<br />

(2) Optional Process IC16 = 1 or 2<br />

The second and third methods are based on the P 1 and B 1 approximation, respectively, <strong>for</strong> fast<br />

neutron spectrum calculation in homogeneous media 24) . By choice of the option IC16= 1 or 2, the<br />

system under study is, first, homogenized by simple smearing of the a<strong>to</strong>mic number densities in the<br />

cell, if IC2>0 is specified, and the P 1 and B 1 equations are solved by assuming an appropriate buckling.<br />

247

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