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

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7.5.2 Spectrum <strong>for</strong> Collapsing<br />

The fluxes thus used are however not taken account of the neutron leakage from the system<br />

under study. So these fluxes should be renormalized <strong>to</strong> take account of the leakage. For this purpose,<br />

the homogenized effective cross-sections are at first calculated without any group collapsing <strong>for</strong> the<br />

whole energy range <strong>to</strong> obtain the homogeneous P 1 or B 1 spectrum.<br />

The P 1 or B 1 equation in multigroup <strong>for</strong>m can be written in the conventional and unified way as<br />

F<br />

1, g<br />

3α<br />

Σ<br />

g<br />

+ Σ<br />

t,<br />

g<br />

tg<br />

F<br />

F<br />

1g<br />

0g<br />

=<br />

G<br />

∑<br />

g ' = 1<br />

2<br />

− B F<br />

Σ<br />

0g<br />

s0g<br />

' →g<br />

=<br />

G<br />

∑<br />

g ' = 1<br />

F<br />

Σ<br />

0g<br />

'<br />

+ Χ<br />

s1g<br />

' →g<br />

F<br />

0g<br />

1g<br />

'<br />

,<br />

(7.5-14)<br />

where α g equals unity <strong>for</strong> the P 1 approximation and is given <strong>for</strong> the B 1 approximation by<br />

α<br />

α<br />

g<br />

g<br />

= ( x<br />

= ( x<br />

g<br />

g<br />

tan<br />

−1<br />

tanh<br />

x<br />

−1<br />

g<br />

x<br />

)<br />

g<br />

)<br />

−1<br />

{ − (tan x ) / x }<br />

3 1<br />

−1<br />

2<br />

{ − (tanh x ) / x } <strong>for</strong> B ≤ 0<br />

3 1<br />

g<br />

g<br />

g<br />

g<br />

<strong>for</strong><br />

B<br />

2<br />

≥ 0<br />

(7.5-15)<br />

with<br />

2<br />

x g B Σt,<br />

g<br />

= ,<br />

where the quantity B 2 is the value entered in Block-4 of Sect.2.2.<br />

Assuming a fission spectrum as the source term. Eq.(7.5-2) is solved by the P 1 or B 1<br />

approximation <strong>for</strong> the fast energy range, while the solution is obtained in the thermal energy range<br />

assuming a slowing-down source. The linked spectrum <strong>for</strong> the whole energy range is optionally used<br />

<strong>to</strong> replace the spectrum of the flux of the cell calculation obtained by assuming an infinite array of<br />

lattice cell.<br />

Using the solution, ϕ i,g , of Eq.(7.4.1-1), the spatially averaged fluxes are calculated by<br />

Φ<br />

g<br />

=<br />

∑<br />

i<br />

i∈cell<br />

V ϕ / V .<br />

(7.5-16)<br />

i,<br />

g<br />

cell<br />

Then, the spectrum which includes the leakage effect can be given by<br />

ϕ ' i, g = ϕi,<br />

g F0<br />

g / Φ g .<br />

(7.5-17)<br />

The resultant spectrum ϕ ’ i,g replaces the infinite spectrum ϕ i,g , if the minus sign of IC9 is entered, and<br />

is used <strong>to</strong> give the microscopic effective cross-section σ<br />

procedure is executed in the HOMOSP routine.<br />

n<br />

z , m,<br />

G<br />

<strong>to</strong> the cell burn-up routine. Above<br />

For the isolated mixture which is not used in the cell calculation, either of the spectra on the<br />

items (a), (b) and (c) in the second paragraph of Sec.7.5 will be chosen <strong>for</strong> the weight.<br />

283

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