| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 8.939 (b) | 9.928 (b) | 1.111 | − | 3.858 (b) | 5.524 (b) |
| 2 | (n,elastic) | 7.656 (b) | 8.643 (b) | 1.129 | − | 2.175 (b) | 4.788 (b) |
| 4 | (n,inelastic) | ( E-thr = 919.3 keV ) | 760.6 (mb) | 729.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.60 MeV ) | 834.5 (mb) | 129.5 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.050 MeV ) | 0.000 (b) | 3.302 (nb) | |||
| 28 | (n,np) | ( E-thr = 7.149 MeV ) | 55.58 (mb) | 46.83 (μb) | |||
| 32 | (n,nd) | ( E-thr = 16.14 MeV ) | − | 6.565e-12 (b) | |||
| 102 | (n,γ) | 1.284 (b) | 1.284 (b) | 1.000 | 862.6 (mb) | 917.7 (μb) | 4.871 (mb) |
| 103 | (n,p) | ( E-thr = 718.3 keV ) | 21.80 (mb) | 249.2 (μb) | |||
| 104 | (n,d) | ( E-thr = 4.899 MeV ) | 932.7 (μb) | 304.0 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.810 MeV ) | 332.3 (nb) | 867.5e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 10.08 MeV ) | 0.000 (b) | 233.7e-15 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 52.44 (μb) | 5.313 (mb) | 3.147 (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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