| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.647 (b) | 5.231 (b) | 1.126 | − | 4.585 (b) | 5.668 (b) |
| 2 | (n,elastic) | 4.522 (b) | 5.105 (b) | 1.129 | − | 2.559 (b) | 4.800 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 565.0 (mb) | 812.4 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.647 MeV ) | 1.440 (b) | 656.4 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.26 MeV ) | − | 35.20 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.402 MeV ) | 136.9 (μb) | 57.83 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.361 MeV ) | 297.7 (μb) | 137.8 (nb) | |||
| 102 | (n,γ) | 125.1 (mb) | 125.2 (mb) | 1.001 | 12.18 (b) | 1.085 (mb) | 53.69 (mb) |
| 103 | (n,p) | ( E-thr = 2.517 MeV ) | 13.09 (mb) | 8.708 (μb) | |||
| 104 | (n,d) | ( E-thr = 7.117 MeV ) | 371.2 (μb) | 87.67 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.920 MeV ) | 13.81 (nb) | 377.8e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 8.440 MeV ) | 55.53e-15 (b) | 20.42e-15 (b) | |||
| 107 | (n,a) | 211.7e-18 (b) | 214.2e-18 (b) | 1.012 | 70.31 (μb) | 5.315 (mb) | 4.190 (μb) |
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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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