| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 8.959 (b) | 9.455 (b) | 1.055 | − | 4.720 (b) | 5.774 (b) |
| 2 | (n,elastic) | 3.738 (b) | 4.219 (b) | 1.129 | − | 2.441 (b) | 4.398 (b) |
| 4 | (n,inelastic) | ( E-thr = 37.41 keV ) | 610.3 (mb) | 1.301 (b) | |||
| 16 | (n,2n) | ( E-thr = 9.039 MeV ) | 1.658 (b) | 1.123 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.90 MeV ) | − | 307.5 (nb) | |||
| 22 | (n,na) | ( E-thr = 3.112 MeV ) | 7.937 (μb) | 3.241 (nb) | |||
| 28 | (n,np) | ( E-thr = 5.833 MeV ) | 725.2 (μb) | 266.4 (nb) | |||
| 102 | (n,γ) | 5.221 (b) | 5.236 (b) | 1.003 | 174.8 (b) | 1.005 (mb) | 73.31 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 355.8 (μb) | 7.856 (mb) | 23.52 (μb) |
| 104 | (n,d) | ( E-thr = 3.590 MeV ) | 1.918 (mb) | 774.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.450 MeV ) | 27.51 (μb) | 16.30 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 17.06 (μb) | 1.980 (mb) | 1.209 (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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