| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.381 (b) | 6.057 (b) | 1.126 | − | 4.692 (b) | 5.734 (b) |
| 2 | (n,elastic) | 5.238 (b) | 5.914 (b) | 1.129 | − | 2.672 (b) | 4.825 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 375.0 (mb) | 888.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.185 MeV ) | 1.640 (b) | 1.452 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.72 MeV ) | − | 433.8 (nb) | |||
| 22 | (n,na) | ( E-thr = 4.851 MeV ) | 2.698 (μb) | 4.695 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.78 MeV ) | 848.1 (nb) | 13.67 (nb) | |||
| 102 | (n,γ) | 143.0 (mb) | 143.1 (mb) | 1.001 | 1.141 (b) | 750.8 (μb) | 17.47 (mb) |
| 103 | (n,p) | ( E-thr = 4.626 MeV ) | 3.417 (mb) | 856.2 (nb) | |||
| 104 | (n,d) | ( E-thr = 8.536 MeV ) | 21.54 (μb) | 14.97 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.84 MeV ) | 77.36e-12 (b) | 92.53e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 11.35 MeV ) | 284.3e-27 (b) | 5.057e-18 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 736.5 (nb) | 418.2 (μb) | 127.5 (nb) |
|
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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