| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 193.6 (b) | 198.8 (b) | 1.027 | − | 6.004 (b) | 8.243 (b) |
| 2 | (n,elastic) | 7.134 (b) | 7.940 (b) | 1.113 | − | 2.838 (b) | 4.641 (b) |
| 4 | (n,inelastic) | ( E-thr = 46.58 keV ) | 303.2 (mb) | 2.424 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.377 MeV ) | 489.4 (mb) | 4.007 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.69 MeV ) | 132.1 (mb) | 16.51 (μb) | |||
| 18 | (n,fission) | 2.502 (b) | 2.511 (b) | 1.004 | 4.879 (b) | 2.239 (b) | 1.029 (b) |
| 19 | (n,f) | 2.502 (b) | 2.511 (b) | 1.004 | 4.445 (b) | 1.291 (b) | 1.008 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 895.5 (mb) | 21.20 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 9.000 MeV ) | 51.78 (mb) | 8.222 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.50 MeV ) | − | 3.395e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 14.00 MeV ) | 0.000 (b) | 4.772 (nb) | |||
| 102 | (n,γ) | 183.9 (b) | 188.4 (b) | 1.024 | 3.821 (kb) | 922.8 (μb) | 143.1 (mb) |
| 456 | νp | 3.881 | − | − | − | 7.213 | − |
| 455 | νd | 4.107e-3 | − | − | − | 2.818e-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.
|