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

1 IREAC1 Reaction type for the numerator of Eq.(2.10-11)
= -1 fix as unity (=1.0)
= 0 fission reaction (Σ x1, g =Σ f, g )
= 1 capture reaction (Σ x1, g =Σ c, g )
= 2 absorption reaction (Σ x1, g =Σ a, g )
= 3 neutron production reaction (Σ x1, g =νΣ f, g )
2 IREAC2 reaction type of the denominator of Eq.(2.10.11)
= -1 fix as unity (=1.0)
= 0 fission reaction (Σ x2, g =Σ f, g )
= 1 capture reaction (Σ x2, g =Σ c, g )
= 2 absorption reaction (Σ x2, g =Σ a, g )
= 3 neutron production reaction (Σ x2, g =νΣ f, g )
Repeat Block-5-3 IOPT(4) times.
An example to use reaction rate calculation option is shown below. A pin rod cell is calculated
by PIJ with 107 group (fast 62, thermal 45 groups) structure where fuel region is sub-divide into 5
R-Regions. Spatial distributions of absorption rate in the whole energy range and thermal fission rate,
and spectrum indexes about U-235 and U-238 will be edited.
---------+---------+---------+---------+---------+--------
3 / NMAT
FUELXX1X 0 3 849.12 0.82 0.0 / l:U02 FUEL
XU050001 2 0 1.05692E-03 / l
XU080001 2 0 2.21466E-02 / 2
X0060001 0 0 4.64071E-02 / 3
CLADXX2X 0 3 586.88 0.13 0.0 / 2:CLADDING
XZRN0001 0 0 3.80326E-02 / l
XCRN0001 0 0 6.71520E-05 / 2
XFEN0001 0 0 1.31290E-04 / 3
MODEXX3X 0 2 578.15 0.00 0.0 / 3 :WATER MODERATOR
XH01H001 0 0 4.78704E-02 / l
X0060001 0 0 2.39352E-02 / 2
& >
l l 5 0 / Block-l
FUELX01X 2 5 / Block-2-1 (total absorption rate distribution)
l 0 0 2 0 0 3 0 0 4 0 0 5 0 0 / Block-2-2
FUELX01X 0 5 / Block-3-1 (thermal fission rate distribution)
l 0 0 2 0 0 3 0 0 4 0 0 5 0 0 / Block-3-2
62(0.0) 45(1.0) / Block-3-3 filter for 62+45=107groups
l 1 2 1 0 0 62(1.0) 45(0.0) / Block-4-1 for spectral index
l 1 2 2 0 0 62(1.0) 45(0.0) / repeat Block-4-1 IOPT(3) times
l 1 2 3 0 0 62(1.0) 45(0.0)
l 1 2 4 0 0 62(1.0) 45(0.0)
l 1 2 5 0 0 62(1.0) 45(0.0)
---------+---------+---------+---------+---------+--------
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