| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 18.34 (b) | 18.64 (b) | 1.016 | − | 2.348 (b) | 3.618 (b) |
| 2 | (n,elastic) | 2.307 (b) | 2.604 (b) | 1.128 | − | 1.088 (b) | 2.989 (b) |
| 4 | (n,inelastic) | ( E-thr = 799.1 keV ) | 653.7 (mb) | 591.5 (mb) | |||
| 16 | (n,2n) | ( E-thr = 13.20 MeV ) | 8.200 (mb) | 1.805 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.729 MeV ) | 326.6 (μb) | 183.5 (nb) | |||
| 28 | (n,np) | ( E-thr = 9.784 MeV ) | 223.7 (mb) | 39.64 (μb) | |||
| 102 | (n,γ) | 16.04 (b) | 16.04 (b) | 1.000 | 7.497 (b) | 894.9 (μb) | 5.255 (mb) |
| 103 | (n,p) | ( E-thr = 260.8 keV ) | 284.3 (mb) | 31.81 (mb) | |||
| 104 | (n,d) | ( E-thr = 7.514 MeV ) | 15.02 (mb) | 4.115 (μb) | |||
| 105 | (n,t) | ( E-thr = 12.92 MeV ) | 10.18e-12 (b) | 607.1e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 8.804 MeV ) | 2.326 (μb) | 1.811 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 12.02 (mb) | 73.21 (mb) | 691.2 (μb) |
| 111 | (n,2p) | ( E-thr = 8.371 MeV ) | 387.5 (μb) | 84.07 (nb) | |||
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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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