| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 8.886 (b) | 9.977 (b) | 1.123 | − | 3.442 (b) | 4.878 (b) |
| 2 | (n,elastic) | 8.456 (b) | 9.546 (b) | 1.129 | − | 1.673 (b) | 3.693 (b) |
| 4 | (n,inelastic) | ( E-thr = 621.7 keV ) | 737.1 (mb) | 1.170 (b) | |||
| 16 | (n,2n) | ( E-thr = 10.63 MeV ) | 1.003 (b) | 274.5 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.15 MeV ) | − | 5.997 (nb) | |||
| 22 | (n,na) | ( E-thr = 6.107 MeV ) | 84.93 (μb) | 58.90 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.53 MeV ) | 574.0 (μb) | 236.4 (nb) | |||
| 102 | (n,γ) | 430.1 (mb) | 430.4 (mb) | 1.001 | 4.701 (b) | 1.075 (mb) | 14.75 (mb) |
| 103 | (n,p) | ( E-thr = 3.471 MeV ) | 17.59 (mb) | 27.14 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.280 MeV ) | 2.022 (mb) | 414.6 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.77 MeV ) | 373.0e-12 (b) | 1.563 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 10.81 MeV ) | 0.000 (b) | 860.1e-15 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 254.4 (μb) | 5.453 (mb) | 9.479 (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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