| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.403 (b) | 7.122 (b) | 1.112 | − | 3.671 (b) | 5.370 (b) |
| 2 | (n,elastic) | 5.575 (b) | 6.294 (b) | 1.129 | − | 1.858 (b) | 4.161 (b) |
| 4 | (n,inelastic) | ( E-thr = 802.8 keV ) | 1.126 (b) | 1.125 (b) | |||
| 16 | (n,2n) | ( E-thr = 12.06 MeV ) | 495.1 (mb) | 67.94 (μb) | |||
| 22 | (n,na) | ( E-thr = 5.238 MeV ) | 406.9 (μb) | 150.3 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.964 MeV ) | 76.06 (mb) | 14.75 (μb) | |||
| 32 | (n,nd) | ( E-thr = 17.80 MeV ) | − | 628.6e-18 (b) | |||
| 102 | (n,γ) | 827.7 (mb) | 828.2 (mb) | 1.001 | 11.43 (b) | 1.726 (mb) | 78.39 (mb) |
| 103 | (n,p) | ( E-thr = 112.8 keV ) | 101.3 (mb) | 5.207 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.713 MeV ) | 3.159 (mb) | 736.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.47 MeV ) | 51.83e-12 (b) | 485.5e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 6.997 MeV ) | 3.470 (nb) | 16.07e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 1.242 (mb) | 9.082 (mb) | 70.46 (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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