| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 254.7 (kb) | 217.0 (kb) | 0.852 | − | 5.699 (b) | 6.980 (b) |
| 2 | (n,elastic) | 1.009 (kb) | 924.7 (b) | 0.916 | − | 3.423 (b) | 4.701 (b) |
| 4 | (n,inelastic) | ( E-thr = 54.85 keV ) | 531.9 (mb) | 2.154 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.406 MeV ) | 1.736 (b) | 10.69 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.00 MeV ) | − | 5.360 (μb) | |||
| 22 | (n,na) | ( E-thr = 694.3 keV ) | 18.38 (μb) | 8.865 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.087 MeV ) | 11.20 (μb) | 14.13 (nb) | |||
| 32 | (n,nd) | ( E-thr = 12.14 MeV ) | 25.93e-21 (b) | 259.4e-12 (b) | |||
| 102 | (n,γ) | 253.7 (kb) | 216.1 (kb) | 0.852 | 761.5 (b) | 1.002 (mb) | 112.8 (mb) |
| 103 | (n,p) | ( E-thr = 581.3 keV ) | 4.450 (mb) | 2.006 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.762 MeV ) | 483.5 (μb) | 123.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 5.912 MeV ) | 23.35 (μb) | 15.04 (nb) | |||
| 107 | (n,a) | 477.5 (μb) | 407.9 (μb) | 0.854 | 7.085 (μb) | 1.173 (mb) | 652.1 (nb) |
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These cross sections are calculated from JENDL-3.3 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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