| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 12.61 (b) | 13.46 (b) | 1.068 | − | 2.706 (b) | 3.746 (b) |
| 2 | (n,elastic) | 6.570 (b) | 7.414 (b) | 1.128 | − | 1.289 (b) | 2.506 (b) |
| 4 | (n,inelastic) | ( E-thr = 291.9 keV ) | 308.1 (mb) | 1.235 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.694 MeV ) | 1.095 (b) | 4.376 (mb) | |||
| 17 | (n,3n) | ( E-thr = 16.91 MeV ) | − | 70.32 (nb) | |||
| 22 | (n,na) | ( E-thr = 8.117 MeV ) | 25.89 (μb) | 28.02 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.25 MeV ) | 2.801 (μb) | 55.78 (nb) | |||
| 32 | (n,nd) | ( E-thr = 16.59 MeV ) | − | 24.76e-12 (b) | |||
| 102 | (n,γ) | 6.002 (b) | 6.005 (b) | 1.000 | 2.809 (b) | 734.1 (μb) | 867.9 (μb) |
| 103 | (n,p) | ( E-thr = 4.477 MeV ) | 9.310 (mb) | 7.907 (μb) | |||
| 104 | (n,d) | ( E-thr = 9.989 MeV ) | 588.9 (μb) | 135.8 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.23 MeV ) | 22.00 (μb) | 5.075 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 15.26 MeV ) | − | 146.0e-18 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 270.9 (μb) | 1.681 (mb) | 11.84 (μb) |
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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 :
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