| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.332 (kb) | 1.338 (kb) | 1.005 | − | 5.987 (b) | 8.180 (b) |
| 2 | (n,elastic) | 10.52 (b) | 11.88 (b) | 1.129 | − | 2.842 (b) | 4.833 (b) |
| 4 | (n,inelastic) | ( E-thr = 61.86 keV ) | 254.2 (mb) | 2.488 (b) | |||
| 16 | (n,2n) | ( E-thr = 4.823 MeV ) | 131.4 (mb) | 12.67 (mb) | |||
| 17 | (n,3n) | ( E-thr = 11.02 MeV ) | 125.2 (mb) | 18.35 (μb) | |||
| 18 | (n,fission) | 1.301 (kb) | 1.303 (kb) | 1.002 | 964.8 (b) | 2.631 (b) | 762.2 (mb) |
| 19 | (n,f) | 1.301 (kb) | 1.303 (kb) | 1.002 | 963.6 (b) | 753.6 (mb) | 677.5 (mb) |
| 20 | (n,nf) | ( E-thr = 1.700 MeV ) | 1.676 (b) | 85.11 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 7.000 MeV ) | 202.3 (mb) | 80.81 (μb) | |||
| 37 | (n,4n) | ( E-thr = 16.15 MeV ) | − | 19.05 (nb) | |||
| 38 | (n,3nf) | ( E-thr = 13.50 MeV ) | 6.419e-12 (b) | 9.374 (nb) | |||
| 102 | (n,γ) | 20.00 (b) | 19.95 (b) | 0.997 | 657.7 (b) | 861.4 (μb) | 83.26 (mb) |
| 456 | νp | 3.839 | − | − | − | 7.171 | − |
| 455 | νd | 1.320e-2 | − | − | − | 9.000e-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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