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

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= 2 In<strong>for</strong>mation <strong>for</strong> debugging<br />

= 3 Detailed in<strong>for</strong>mation <strong>for</strong> debugging<br />

IBC5<br />

Definition of instantaneous conversion ratio<br />

= 0 Use defaulted definition of conversion ratio<br />

= 1 Conversion ratio is redefined by entries of Block-7-1 through -7-3<br />

Note:<br />

Generally, an instantaneous conversion ratio is defined as the ratio of<br />

production rate <strong>to</strong> depletion rate of fissile nuclides as follows:<br />

FISSProduction( t)<br />

Instantaneous CR( t ) = . (2.11-1)<br />

FISSDepletion( t)<br />

In the SRAC, the user can flexibly define the numera<strong>to</strong>r and denomina<strong>to</strong>r of<br />

Eq.(2.11-1). They are calculated by Eqs.(2.11-2) and (2.11-3), respectively. (Both<br />

are the same function <strong>for</strong>ms)<br />

⎡<br />

⎤<br />

i i i<br />

i i i<br />

∫ ⎢∑ ∑{ α < N ( t)<br />

> σ x(<br />

i g ( t)<br />

Φ g ( t)<br />

+ β λ N } ⎥ dV<br />

FISSP ( t)<br />

=<br />

),<br />

⎢⎣<br />

g i∈Specified<br />

⎥⎦<br />

(2.11-2)<br />

⎡<br />

FISSD ( t)<br />

= ∫ ⎢∑ ∑<br />

x(<br />

j),<br />

⎢⎣<br />

g j∈Specified<br />

⎤<br />

j j j<br />

j j j<br />

{ α < N ( t)<br />

> σ ( t)<br />

Φ ( t)<br />

+ β λ N } ⎥ dV<br />

g<br />

g<br />

⎥⎦<br />

(2.11-3)<br />

where,<br />

i , j : any nuclides selected from the burn-up chain library used,<br />

α , β : arbitrary fac<strong>to</strong>rs defined by user, which are used <strong>to</strong> consider<br />

branching ratio or <strong>to</strong> cut of unnecessary terms (e.g. β = 0.0),<br />

< N i > : a<strong>to</strong>mic number density of nuclide i or 1.0 <strong>to</strong> define microscopic<br />

reaction rate,<br />

i<br />

x ( i)<br />

σ : microscopic cross-section of nuclide i <strong>for</strong> reaction type x. The<br />

reaction type is determined by user depending on nuclide i,<br />

λ : decay constant of each nuclide whose value is defined in the<br />

burn-up chain library. (cf. Sect.3.3)<br />

Furthermore, integrated conversion ratio is also calculated as follows:<br />

137

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