| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 6.330 (b) | 6.798 (b) | 1.074 | − | 3.841 (b) | 4.939 (b) |
| 2 | (n,elastic) | 3.639 (b) | 4.107 (b) | 1.128 | − | 2.508 (b) | 3.566 (b) |
| 4 | (n,inelastic) | ( E-thr = 279.4 keV ) | 268.0 (mb) | 1.348 (b) | |||
| 16 | (n,2n) | ( E-thr = 10.29 MeV ) | 1.029 (b) | 401.7 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.28 MeV ) | − | 24.54 (nb) | |||
| 22 | (n,na) | ( E-thr = 6.563 MeV ) | 28.42 (μb) | 17.85 (nb) | |||
| 28 | (n,np) | ( E-thr = 7.602 MeV ) | 9.470 (mb) | 3.059 (μb) | |||
| 32 | (n,nd) | ( E-thr = 15.30 MeV ) | − | 94.29e-12 (b) | |||
| 33 | (n,nt) | ( E-thr = 16.09 MeV ) | − | 2.060e-12 (b) | |||
| 102 | (n,γ) | 2.691 (b) | 2.691 (b) | 1.000 | 46.63 (b) | 1.004 (mb) | 22.06 (mb) |
| 103 | (n,p) | ( E-thr = 812.5 keV ) | 20.73 (mb) | 225.5 (μb) | |||
| 104 | (n,d) | ( E-thr = 5.263 MeV ) | 425.1 (μb) | 127.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.041 MeV ) | 1.897 (μb) | 7.111 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 70.92 (μb) | 4.259 (mb) | 3.500 (μb) |
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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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