| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 154.3 (b) | 158.0 (b) | 1.024 | − | 5.832 (b) | 7.683 (b) |
| 2 | (n,elastic) | 31.30 (b) | 35.14 (b) | 1.122 | − | 2.751 (b) | 4.768 (b) |
| 4 | (n,inelastic) | ( E-thr = 58.01 keV ) | 498.4 (mb) | 2.398 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.137 MeV ) | 1.897 (b) | 7.389 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.62 MeV ) | 85.78 (mb) | 23.13 (μb) | |||
| 18 | (n,fission) | 150.1 (mb) | 150.2 (mb) | 1.001 | 1.382 (b) | 598.9 (mb) | 375.7 (mb) |
| 19 | (n,f) | 150.1 (mb) | 150.2 (mb) | 1.001 | 1.275 (b) | 308.6 (mb) | 371.7 (mb) |
| 20 | (n,nf) | ( E-thr = 2.500 MeV ) | 289.2 (mb) | 3.943 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 10.00 MeV ) | 551.2 (μb) | 1.899 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 17.00 MeV ) | − | 483.6e-21 (b) | |||
| 102 | (n,γ) | 122.9 (b) | 122.7 (b) | 0.999 | 1.123 (kb) | 1.233 (mb) | 132.2 (mb) |
| 456 | νp | 1.813 | − | − | − | 3.636 | − |
| 455 | νd | 1.115e-2 | − | − | − | 7.689e-3 | − |
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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.
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