| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.528 (b) | 6.856 (b) | 1.050 | − | 4.973 (b) | 5.884 (b) |
| 2 | (n,elastic) | 2.519 (b) | 2.844 (b) | 1.129 | − | 3.454 (b) | 4.784 (b) |
| 4 | (n,inelastic) | ( E-thr = 568.7 keV ) | 253.1 (mb) | 990.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 9.954 MeV ) | 1.249 (b) | 551.9 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.19 MeV ) | − | 297.0 (nb) | |||
| 22 | (n,na) | ( E-thr = 1.081 MeV ) | 1.736 (mb) | 685.2 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.076 MeV ) | 728.5 (μb) | 200.3 (nb) | |||
| 102 | (n,γ) | 4.009 (b) | 4.012 (b) | 1.001 | 88.78 (b) | 1.115 (mb) | 103.0 (mb) |
| 103 | (n,p) | ( E-thr = 1.208 MeV ) | 9.513 (mb) | 12.87 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.746 MeV ) | 273.3 (μb) | 81.84 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.830 MeV ) | 667.9 (nb) | 5.339 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 6.108 MeV ) | 1.615e-12 (b) | 6.643e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 680.5 (μb) | 6.164 (mb) | 51.02 (μb) |
|
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 :
|