| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 60.80 (kb) | 51.30 (kb) | 0.844 | − | 5.699 (b) | 6.981 (b) |
| 2 | (n,elastic) | 59.02 (b) | 57.26 (b) | 0.970 | − | 3.423 (b) | 4.632 (b) |
| 4 | (n,inelastic) | ( E-thr = 60.39 keV ) | 472.0 (mb) | 2.118 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.485 MeV ) | 1.795 (b) | 8.039 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.20 MeV ) | − | 4.261 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 20.41 (nb) | 72.00 (μb) | 25.62 (nb) |
| 28 | (n,np) | ( E-thr = 7.688 MeV ) | 27.01 (μb) | 21.68 (nb) | |||
| 32 | (n,nd) | ( E-thr = 11.84 MeV ) | 409.2e-21 (b) | 475.3e-12 (b) | |||
| 102 | (n,γ) | 60.74 (kb) | 51.24 (kb) | 0.844 | 1.534 (kb) | 1.004 (mb) | 222.5 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 67.58 (μb) | 5.458 (mb) | 3.762 (μb) |
| 104 | (n,d) | ( E-thr = 5.363 MeV ) | 773.1 (μb) | 178.6 (nb) | |||
| 105 | (n,t) | ( E-thr = 5.619 MeV ) | 26.75 (μb) | 15.31 (nb) | |||
| 107 | (n,a) | 81.75 (μb) | 69.03 (μb) | 0.845 | 24.52 (μb) | 1.922 (mb) | 2.864 (μb) |
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These cross sections are calculated from JENDL-3.3 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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