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

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For a special case where the NRA is applicable <strong>to</strong> the slowing down of absorber, the first-order<br />

solution can be written in the conventional <strong>for</strong>m<br />

σ p + σ b<br />

ϕ( u)<br />

≅<br />

(7.3.1-3)<br />

σ ( u)<br />

+ σ<br />

t<br />

b<br />

This first-order solution is usually adopted <strong>to</strong> construct a cross-section set of the Bondarenko<br />

type 51) with the resonance shielding fac<strong>to</strong>rs <strong>for</strong> use in fast reac<strong>to</strong>r analysis. For the higher energy<br />

region, say E > 130 eV, the NRA is considered <strong>to</strong> be a reasonable approximation <strong>for</strong> heavy nuclides.<br />

That is, the flux of Eq.(7.3.1-3) does not so much deviate from the exact one of Eq.(7.3.1-1) in the<br />

meaning of the weighting function <strong>for</strong> cross-section averaging. On the other hand, <strong>for</strong> the light and<br />

intermediate mass nuclides with resonance structure, the SRAC library has been generated assuming<br />

the spectrum of Eq.(7.3.1-3). In fact, no simple and convenient spectrum has been proposed <strong>to</strong> treat<br />

these nuclides. Since the resonance structure of light and intermediate mass nuclide is of minor<br />

importance in thermal and intermediate reac<strong>to</strong>rs, the present treatment will, in practice, be sufficient.<br />

Hence, we can think of Eq.(7.3.1-3) as representing a standard <strong>for</strong>m of weighting spectrum <strong>for</strong> the<br />

higher energy regions.<br />

For a homogeneous system including many modera<strong>to</strong>r nuclides, the slowing down equation can<br />

be written as<br />

1<br />

u m<br />

s ∑ j j j<br />

(7.3.1-4)<br />

n<br />

{ σ ( ) + σ } ϕ(<br />

u)<br />

= K(<br />

σ ϕ)<br />

+ n σ K ( ϕ)<br />

t<br />

f<br />

j<br />

where<br />

σ<br />

m<br />

1<br />

=<br />

n<br />

f<br />

∑<br />

j<br />

n σ<br />

j<br />

j<br />

(7.3.1-5)<br />

and K j is the slowing down kernel <strong>for</strong> modera<strong>to</strong>r j; n f and n j are the a<strong>to</strong>mic number density of absorber<br />

and modera<strong>to</strong>r nuclides, respectively.<br />

When the NRA is applicable <strong>to</strong> the slowing down of modera<strong>to</strong>rs (referred <strong>to</strong> as NRA modera<strong>to</strong>r),<br />

we have<br />

{ σ t u)<br />

+ σ m} ϕ(<br />

u)<br />

= K ( σ sϕ)<br />

+ σ m<br />

( (7.3.1-6)<br />

Consequently, a homogeneous system with the NRA modera<strong>to</strong>rs has the same effective<br />

cross-section as the homogeneous system described by Eq.(7.3.1-1). That is, the effective<br />

cross-sections can be calculated by calculating σ m as <strong>to</strong> be used <strong>for</strong> the table-look-up of the resonance<br />

shielding tables. Here, it should be noted that the slowing down of absorber is still accurately<br />

estimated in the present treatment.<br />

250

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