| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.198 (b) | 5.735 (b) | 1.103 | − | 3.713 (b) | 5.138 (b) |
| 2 | (n,elastic) | 4.158 (b) | 4.694 (b) | 1.129 | − | 1.942 (b) | 4.235 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.089 MeV ) | 931.3 (mb) | 879.0 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.63 MeV ) | 786.6 (mb) | 120.6 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.434 MeV ) | 6.676 (μb) | 15.18 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.758 MeV ) | 2.416 (mb) | 636.9 (nb) | |||
| 102 | (n,γ) | 1.040 (b) | 1.041 (b) | 1.001 | 4.804 (b) | 998.8 (μb) | 22.20 (mb) |
| 103 | (n,p) | ( E-thr = 1.006 MeV ) | 46.60 (mb) | 547.5 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.508 MeV ) | 868.8 (μb) | 189.6 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.79 MeV ) | 0.000 (b) | 233.0e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 9.058 MeV ) | 0.000 (b) | 360.1e-15 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 98.37 (μb) | 1.963 (mb) | 3.873 (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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