| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.61 (b) | 13.63 (b) | 1.081 | − | 3.479 (b) | 5.193 (b) |
| 2 | (n,elastic) | 7.881 (b) | 8.896 (b) | 1.129 | − | 1.617 (b) | 3.639 (b) |
| 4 | (n,inelastic) | ( E-thr = 460.9 keV ) | 1.012 (b) | 1.464 (b) | |||
| 16 | (n,2n) | ( E-thr = 12.24 MeV ) | 274.6 (mb) | 34.06 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.449 MeV ) | 3.713 (mb) | 982.7 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.340 MeV ) | 365.7 (mb) | 102.6 (μb) | |||
| 32 | (n,nd) | ( E-thr = 17.25 MeV ) | − | 87.16e-15 (b) | |||
| 102 | (n,γ) | 4.732 (b) | 4.734 (b) | 1.000 | 26.36 (b) | 2.227 (mb) | 69.41 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 154.5 (mb) | 183.5 (mb) | 19.00 (mb) |
| 104 | (n,d) | ( E-thr = 6.087 MeV ) | 2.573 (mb) | 594.1 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.91 MeV ) | 183.0 (nb) | 1.177 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 5.862 MeV ) | 85.70 (nb) | 37.18e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 9.336 (mb) | 17.44 (mb) | 793.7 (μb) |
|
These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
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