| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 118.2 (b) | 118.3 (b) | 1.001 | − | 5.874 (b) | 7.785 (b) |
| 2 | (n,elastic) | 17.82 (b) | 19.80 (b) | 1.111 | − | 2.720 (b) | 4.720 (b) |
| 4 | (n,inelastic) | ( E-thr = 43.69 keV ) | 474.1 (mb) | 1.729 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.874 MeV ) | 605.0 (mb) | 2.573 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.66 MeV ) | 5.367 (mb) | 2.424 (μb) | |||
| 18 | (n,fission) | 67.02 (mb) | 65.80 (mb) | 0.982 | 5.195 (b) | 2.066 (b) | 1.222 (b) |
| 19 | (n,f) | 67.02 (mb) | 65.80 (mb) | 0.982 | 4.679 (b) | 735.8 (mb) | 1.198 (b) |
| 20 | (n,nf) | ( E-thr = 4.000 MeV ) | 1.168 (b) | 24.30 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 11.00 MeV ) | 162.6 (mb) | 23.66 (μb) | |||
| 38 | (n,3nf) | ( E-thr = 16.50 MeV ) | − | 8.342 (nb) | |||
| 102 | (n,γ) | 100.3 (b) | 98.39 (b) | 0.981 | 609.5 (b) | 856.1 (μb) | 108.2 (mb) |
| 456 | νp | 2.354 | − | − | − | 4.230 | − |
| 455 | νd | 1.053e-2 | − | − | − | 7.930e-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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