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

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MACROWRK file.<br />

2 INTSTP Step number <strong>to</strong> read the composition. Enter 0 if the burn-up step tag (b-tag) is ’0’.<br />

The b-tags (cf. Sect.2.9) correspond <strong>to</strong> burn-up step numbers as:<br />

(b-tag=0, 1,…,9, A, B,…,Z, a, b,….,z ⇒ 0, 1,….,9, 10, 11, …35, 36, 37,....,61)<br />

Block-7-1 Required if IBC5=1 /2/<br />

1 NFIS Number of nuclides <strong>to</strong> contribute <strong>to</strong> depletion of fissile nuclides<br />

See Eq.(2.11-3) and burn-up chain model (cf. Sect.3.3)<br />

2 NFER Number of nuclides <strong>to</strong> contribute <strong>to</strong> production of fissile nuclides<br />

See Eq.(2.11-2) and burn-up chain model (cf. Sect.3.3)<br />

Block-7-2 Required if IBC5=1 /A4, 1, 1/<br />

1 NAMFIS Nuclide name and reaction type <strong>to</strong> contribute <strong>to</strong> depletion of fissile nuclides by 4<br />

characters. The first 3 characters are <strong>for</strong> nuclide name and the fourth character <strong>for</strong><br />

reaction type (Fission/ Capture/ Absorption/ N2N/ Decay). Enter as ‘U05A’,<br />

‘U08C’, ‘PU1D’. If ‘D’ is specified, contribution of decay is included in the<br />

calculation of conversion ratio whereas this contribution is not taken in<strong>to</strong> account<br />

<strong>for</strong> the tabulated absorption cross-section of fissile material (<br />

fissile<br />

Σ a,g<br />

) <strong>to</strong> be s<strong>to</strong>red in<br />

MACRO file.<br />

Note:<br />

Nuclide name and reaction type should be appropriately selected by taking in<strong>to</strong><br />

account the burn-up chain model used in the calculation. (cf. Sect.3.3)<br />

The fissile absorption cross-section (<br />

conversion ratio.<br />

fissile<br />

Σ a,g<br />

) is used by COREBN <strong>to</strong> calculate<br />

2 IFISFLG<br />

= 0 Do not multiply a<strong>to</strong>mic number density of this nuclide (microscopic<br />

cross-sections are used)<br />

= 1 Multiply a<strong>to</strong>mic number density of this nuclide (macroscopic<br />

cross-sections are used)<br />

3 FISFACT The fac<strong>to</strong>r <strong>to</strong> indicate sign or branching ratio. If Block-7-2 are entered as below, the<br />

summation of the values in parentheses is defined as the depletion rate of fissile<br />

141

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