| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.211 (kb) | 2.227 (kb) | 1.007 | − | 5.986 (b) | 8.228 (b) |
| 2 | (n,elastic) | 10.32 (b) | 11.66 (b) | 1.130 | − | 2.852 (b) | 4.495 (b) |
| 4 | (n,inelastic) | ( E-thr = 60.24 keV ) | 269.4 (mb) | 1.482 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.311 MeV ) | 293.2 (mb) | 15.86 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.12 MeV ) | 5.250 (mb) | 1.131 (μb) | |||
| 18 | (n,fission) | 2.001 (kb) | 2.012 (kb) | 1.006 | 1.605 (kb) | 2.559 (b) | 2.178 (b) |
| 19 | (n,f) | 2.001 (kb) | 2.012 (kb) | 1.006 | 1.605 (kb) | 1.481 (b) | 2.169 (b) |
| 20 | (n,nf) | ( E-thr = 2.500 MeV ) | 892.3 (mb) | 8.817 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.500 MeV ) | 190.2 (mb) | 32.78 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.17 MeV ) | − | 5.726e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 15.00 MeV ) | − | 497.4e-12 (b) | |||
| 102 | (n,γ) | 200.1 (b) | 201.3 (b) | 1.006 | 157.0 (b) | 784.3 (μb) | 56.93 (mb) |
| 456 | νp | 4.141 | − | − | − | 7.389 | − |
| 455 | νd | 2.818e-3 | − | − | − | 1.938e-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.
|