| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.168 (kb) | 2.176 (kb) | 1.004 | − | 5.998 (b) | 8.256 (b) |
| 2 | (n,elastic) | 10.22 (b) | 11.54 (b) | 1.129 | − | 2.882 (b) | 4.581 (b) |
| 4 | (n,inelastic) | ( E-thr = 80.42 keV ) | 255.9 (mb) | 1.639 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.113 MeV ) | 418.7 (mb) | 19.42 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.49 MeV ) | 56.42 (mb) | 8.295 (μb) | |||
| 18 | (n,fission) | 2.129 (kb) | 2.133 (kb) | 1.002 | 1.122 (kb) | 2.379 (b) | 1.931 (b) |
| 19 | (n,f) | 2.129 (kb) | 2.133 (kb) | 1.002 | 1.121 (kb) | 1.364 (b) | 1.924 (b) |
| 20 | (n,nf) | ( E-thr = 2.500 MeV ) | 741.3 (mb) | 7.709 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 274.4 (mb) | 51.97 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.80 MeV ) | − | 7.147 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 2.511 (nb) | |||
| 102 | (n,γ) | 28.31 (b) | 28.33 (b) | 1.001 | 682.7 (b) | 837.0 (μb) | 83.09 (mb) |
| 456 | νp | 4.077 | − | − | − | 7.493 | − |
| 455 | νd | 5.999e-3 | − | − | − | 4.107e-3 | − |
|
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 :
νp,
νd
: numbers of prompt and delayed neutrons per fission.
|