| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 207.2 (b) | 207.9 (b) | 1.003 | − | 5.382 (b) | 6.821 (b) |
| 2 | (n,elastic) | 950.2 (mb) | 1.111 (b) | 1.169 | − | 2.254 (b) | 4.441 (b) |
| 4 | (n,inelastic) | ( E-thr = 123.8 keV ) | 1.352 (b) | 2.275 (b) | |||
| 16 | (n,2n) | ( E-thr = 8.318 MeV ) | 1.770 (b) | 2.766 (mb) | |||
| 17 | (n,3n) | ( E-thr = 13.96 MeV ) | 0.000 (b) | 12.53 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 336.6 (nb) | 198.9 (μb) | 76.27 (nb) |
| 28 | (n,np) | ( E-thr = 8.726 MeV ) | 3.508 (μb) | 20.17 (nb) | |||
| 33 | (n,nt) | ( E-thr = 13.74 MeV ) | 0.000 (b) | 3.730e-12 (b) | |||
| 102 | (n,γ) | 206.3 (b) | 206.8 (b) | 1.003 | 2.764 (kb) | 1.148 (mb) | 98.41 (mb) |
| 103 | (n,p) | ( E-thr = 2.706 MeV ) | 2.902 (mb) | 858.5 (nb) | |||
| 104 | (n,d) | ( E-thr = 6.401 MeV ) | 136.5 (μb) | 103.3 (nb) | |||
| 105 | (n,t) | ( E-thr = 8.139 MeV ) | 3.584 (μb) | 11.35 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 5.846 (μb) | 1.626 (mb) | 639.4 (nb) |
|
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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