| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.113 (kb) | 3.121 (kb) | 1.003 | − | 5.954 (b) | 8.026 (b) |
| 2 | (n,elastic) | 10.62 (b) | 11.99 (b) | 1.129 | − | 2.732 (b) | 4.604 (b) |
| 4 | (n,inelastic) | ( E-thr = 44.18 keV ) | 346.7 (mb) | 1.126 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.397 MeV ) | 106.2 (mb) | 253.5 (μb) | |||
| 17 | (n,3n) | ( E-thr = 13.59 MeV ) | 9.136 (μb) | 162.2 (nb) | |||
| 18 | (n,fission) | 1.401 (kb) | 1.402 (kb) | 1.001 | 603.7 (b) | 2.769 (b) | 2.170 (b) |
| 19 | (n,f) | 1.401 (kb) | 1.402 (kb) | 1.001 | 603.4 (b) | 1.899 (b) | 2.158 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 867.7 (mb) | 12.16 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 10.00 MeV ) | 1.697 (mb) | 992.3 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 16.00 MeV ) | − | 4.106e-12 (b) | |||
| 102 | (n,γ) | 1.701 (kb) | 1.703 (kb) | 1.001 | 722.1 (b) | 1.013 (mb) | 122.7 (mb) |
| 456 | νp | 3.771 | − | − | − | 6.515 | − |
| 455 | νd | 9.520e-4 | − | − | − | 6.600e-4 | − |
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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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