| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.444 (b) | 3.801 (b) | 1.104 | − | 5.078 (b) | 6.272 (b) |
| 2 | (n,elastic) | 2.763 (b) | 3.120 (b) | 1.129 | − | 2.840 (b) | 5.301 (b) |
| 4 | (n,inelastic) | ( E-thr = 824.7 keV ) | 590.2 (mb) | 929.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.180 MeV ) | 1.640 (b) | 1.120 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.21 MeV ) | − | 1.092 (μb) | |||
| 22 | (n,na) | ( E-thr = 2.057 MeV ) | 106.4 (μb) | 31.45 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.598 MeV ) | 41.39 (μb) | 34.21 (nb) | |||
| 102 | (n,γ) | 680.5 (mb) | 680.7 (mb) | 1.000 | 1.916 (b) | 1.016 (mb) | 36.80 (mb) |
| 103 | (n,p) | ( E-thr = 1.779 MeV ) | 5.062 (mb) | 2.843 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.271 MeV ) | 222.9 (μb) | 73.74 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.937 MeV ) | 214.6 (nb) | 4.973 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 22.06 (μb) | 1.637 (mb) | 1.399 (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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