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Calculation of Macroscopic Cross Section and Mean Free Path | Up
Nuclear Physics and Reactor Theory Volume 1 of 2 | Next
Effects of Temperature on Cross Section |
a
NAl
a,Al
NSi
a,Si
5.64 x 1022atoms
cm3
0.23 x 1024 cm2
2.85 x 1021atoms
cm3
0.16 x 1024 cm2
0.0134 cm1
s
NAl
s,Al
NSi
s,Si
5.64 x 1022atoms
cm3
1.49 x 1024 cm2
2.85 x 1021atoms
cm3
2.20 x 1024 cm2
0.0903 cm1
a
1
a
1
0.01345 cm1
74.3 cm
s
1
s
1
0.0903 cm1
11.1 cm
DOE-HDBK-1019/1-93
Reactor Theory (Neutron Characteristics)
NUCLEAR CROSS SECTIONS AND NEUTRON FLUX
Rev. 0
Page 13
NP-02
Step 2:
The macroscopic cross sections for absorption and scattering are
calculated using Equation (2-4).
Step 3:
The mean free paths are calculated by inserting the macroscopic cross
sections calculated above into Equation (2-3).
Thus, a neutron must travel an average of 74.3 cm to interact by absorption in this alloy, but it
must travel only 11.1 cm to interact by scattering.
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