| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 59.14 (b) | 60.14 (b) | 1.017 | − | 3.307 (b) | 4.419 (b) |
| 2 | (n,elastic) | 7.325 (b) | 8.263 (b) | 1.128 | − | 1.575 (b) | 3.252 (b) |
| 4 | (n,inelastic) | ( E-thr = 643.4 keV ) | 998.5 (mb) | 1.097 (b) | |||
| 16 | (n,2n) | ( E-thr = 12.23 MeV ) | 310.0 (mb) | 38.93 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.130 MeV ) | 15.14 (mb) | 5.292 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.662 MeV ) | 227.7 (mb) | 54.04 (μb) | |||
| 32 | (n,nd) | ( E-thr = 17.35 MeV ) | − | 100.8e-15 (b) | |||
| 102 | (n,γ) | 51.82 (b) | 51.88 (b) | 1.001 | 580.3 (b) | 1.557 (mb) | 57.05 (mb) |
| 103 | (n,p) | ( E-thr = 578.2 keV ) | 148.3 (mb) | 11.53 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.407 MeV ) | 7.763 (mb) | 1.964 (μb) | |||
| 105 | (n,t) | ( E-thr = 11.01 MeV ) | 94.76 (nb) | 849.9e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 6.575 MeV ) | 201.4 (nb) | 73.99e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 14.24 (mb) | 21.95 (mb) | 1.167 (mb) |
|
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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