| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.914 (b) | 5.554 (b) | 1.130 | − | 4.859 (b) | 6.102 (b) |
| 2 | (n,elastic) | 4.820 (b) | 5.442 (b) | 1.129 | − | 2.902 (b) | 5.266 (b) |
| 4 | (n,inelastic) | ( E-thr = 105.0 keV ) | 270.3 (mb) | 827.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 8.259 MeV ) | 1.686 (b) | 3.159 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.04 MeV ) | − | 2.866 (μb) | |||
| 22 | (n,na) | ( E-thr = 7.777 MeV ) | 16.89e-12 (b) | 7.867e-12 (b) | |||
| 28 | (n,np) | ( E-thr = 12.93 MeV ) | 48.61e-18 (b) | 404.3e-12 (b) | |||
| 102 | (n,γ) | 90.03 (mb) | 90.08 (mb) | 1.001 | 96.38 (mb) | 798.5 (μb) | 3.662 (mb) |
| 103 | (n,p) | ( E-thr = 7.484 MeV ) | 87.67 (μb) | 33.42 (nb) | |||
| 104 | (n,d) | ( E-thr = 10.69 MeV ) | 16.84 (nb) | 1.576 (nb) | |||
| 105 | (n,t) | ( E-thr = 12.12 MeV ) | 526.4e-18 (b) | 9.892e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 16.30 MeV ) | − | 247.2e-30 (b) | |||
| 107 | (n,a) | ( E-thr = 3.087 MeV ) | 933.0 (nb) | 722.8e-12 (b) | |||
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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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