| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 5.442 (b) | 5.883 (b) | 1.081 | − | 5.078 (b) | 6.272 (b) |
| 2 | (n,elastic) | 3.440 (b) | 3.881 (b) | 1.128 | − | 2.775 (b) | 5.066 (b) |
| 4 | (n,inelastic) | ( E-thr = 609.3 keV ) | 747.7 (mb) | 1.065 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.546 MeV ) | 1.543 (b) | 741.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 16.79 MeV ) | − | 627.8 (nb) | |||
| 22 | (n,na) | ( E-thr = 1.520 MeV ) | 410.9 (μb) | 109.9 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.234 MeV ) | 184.5 (μb) | 64.71 (nb) | |||
| 102 | (n,γ) | 2.003 (b) | 2.002 (b) | 1.000 | 24.77 (b) | 1.506 (mb) | 138.2 (mb) |
| 103 | (n,p) | ( E-thr = 1.286 MeV ) | 6.837 (mb) | 8.305 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.907 MeV ) | 253.0 (μb) | 84.65 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.733 MeV ) | 517.9 (nb) | 4.517 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 122.4 (μb) | 2.904 (mb) | 8.150 (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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