| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.487 (b) | 6.196 (b) | 1.129 | − | 4.534 (b) | 5.608 (b) |
| 2 | (n,elastic) | 5.336 (b) | 6.024 (b) | 1.129 | − | 2.829 (b) | 4.305 (b) |
| 4 | (n,inelastic) | ( E-thr = 272.9 keV ) | 123.9 (mb) | 1.279 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.552 MeV ) | 1.577 (b) | 2.712 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.52 MeV ) | − | 6.762 (μb) | |||
| 22 | (n,na) | ( E-thr = 5.242 MeV ) | 2.298 (μb) | 3.053 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.19 MeV ) | 158.0 (nb) | 3.786 (nb) | |||
| 102 | (n,γ) | 145.1 (mb) | 145.1 (mb) | 1.001 | 2.004 (b) | 1.003 (mb) | 14.31 (mb) |
| 103 | (n,p) | ( E-thr = 5.573 MeV ) | 2.830 (mb) | 641.2 (nb) | |||
| 104 | (n,d) | ( E-thr = 8.860 MeV ) | 676.0 (nb) | 5.830 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.61 MeV ) | 14.86 (nb) | 1.244 (nb) | |||
| 107 | (n,a) | ( E-thr = 69.44 keV ) | 559.1 (μb) | 127.3 (nb) | |||
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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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