| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 427.1 (b) | 429.3 (b) | 1.005 | − | 5.401 (b) | 6.835 (b) |
| 2 | (n,elastic) | 6.723 (b) | 7.586 (b) | 1.128 | − | 3.047 (b) | 4.480 (b) |
| 4 | (n,inelastic) | ( E-thr = 7.549 keV ) | 698.2 (mb) | 2.308 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.911 MeV ) | 1.649 (b) | 15.42 (mb) | |||
| 17 | (n,3n) | ( E-thr = 14.23 MeV ) | − | 2.595 (μb) | |||
| 22 | (n,na) | ( E-thr = 608.9 keV ) | 57.26 (μb) | 27.47 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.617 MeV ) | 16.39 (μb) | 34.19 (nb) | |||
| 32 | (n,nd) | ( E-thr = 12.31 MeV ) | 11.78e-21 (b) | 576.0e-12 (b) | |||
| 102 | (n,γ) | 420.2 (b) | 420.2 (b) | 1.000 | 720.9 (b) | 1.000 (mb) | 31.18 (mb) |
| 103 | (n,p) | ( E-thr = 1.021 MeV ) | 2.363 (mb) | 934.9 (nb) | |||
| 104 | (n,d) | ( E-thr = 6.292 MeV ) | 1.177 (mb) | 323.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 6.085 MeV ) | 90.29 (μb) | 63.62 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.459 (μb) | 768.8 (μb) | 281.0 (nb) |
|
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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