| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.411 (kb) | 2.271 (kb) | 0.942 | − | 5.946 (b) | 8.043 (b) |
| 2 | (n,elastic) | 10.25 (b) | 11.45 (b) | 1.117 | − | 2.827 (b) | 4.508 (b) |
| 4 | (n,inelastic) | ( E-thr = 55.04 keV ) | 332.4 (mb) | 1.704 (b) | |||
| 16 | (n,2n) | ( E-thr = 5.543 MeV ) | 410.3 (mb) | 8.059 (mb) | |||
| 17 | (n,3n) | ( E-thr = 12.37 MeV ) | 11.50 (mb) | 2.483 (μb) | |||
| 18 | (n,fission) | 2.054 (kb) | 1.935 (kb) | 0.942 | 831.7 (b) | 2.360 (b) | 1.754 (b) |
| 19 | (n,f) | 2.054 (kb) | 1.935 (kb) | 0.942 | 831.3 (b) | 1.089 (b) | 1.739 (b) |
| 20 | (n,nf) | ( E-thr = 2.300 MeV ) | 995.2 (mb) | 15.51 (mb) | |||
| 21 | (n,2nf) | ( E-thr = 6.500 MeV ) | 274.1 (mb) | 77.86 (μb) | |||
| 37 | (n,4n) | ( E-thr = 18.09 MeV ) | − | 96.71e-12 (b) | |||
| 38 | (n,3nf) | ( E-thr = 15.50 MeV ) | − | 317.1e-12 (b) | |||
| 102 | (n,γ) | 347.0 (b) | 324.4 (b) | 0.935 | 107.9 (b) | 958.1 (μb) | 67.87 (mb) |
| 456 | νp | 3.590 | − | − | − | 5.241 | − |
| 455 | νd | 6.482e-3 | − | − | − | 5.227e-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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