| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.893 (kb) | 1.928 (kb) | 1.019 | − | 5.853 (b) | 7.604 (b) |
| 2 | (n,elastic) | 12.03 (b) | 13.60 (b) | 1.131 | − | 2.799 (b) | 4.277 (b) |
| 4 | (n,inelastic) | ( E-thr = 60.26 keV ) | 328.6 (mb) | 1.381 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.820 MeV ) | 617.1 (mb) | 6.521 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.95 MeV ) | 628.6 (μb) | 1.420 (μb) | |||
| 18 | (n,fission) | 1.500 (kb) | 1.526 (kb) | 1.017 | 934.2 (b) | 2.108 (b) | 1.812 (b) |
| 19 | (n,f) | 1.500 (kb) | 1.526 (kb) | 1.017 | 933.9 (b) | 1.247 (b) | 1.803 (b) |
| 20 | (n,nf) | ( E-thr = 3.000 MeV ) | 663.1 (mb) | 8.580 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 8.000 MeV ) | 196.6 (mb) | 27.29 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.95 MeV ) | − | 1.114e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 16.50 MeV ) | − | 6.186e-12 (b) | |||
| 102 | (n,γ) | 380.1 (b) | 386.6 (b) | 1.017 | 235.3 (b) | 1.043 (mb) | 126.6 (mb) |
| 456 | νp | 2.272 | − | − | − | 3.672 | − |
| 455 | νd | 7.460e-3 | − | − | − | 5.150e-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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