| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.329 (b) | 4.515 (b) | 1.043 | − | 2.760 (b) | 3.611 (b) |
| 2 | (n,elastic) | 1.429 (b) | 1.613 (b) | 1.129 | − | 1.340 (b) | 3.150 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.355 MeV ) | 657.0 (mb) | 450.9 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.58 MeV ) | 388.1 (mb) | 57.86 (μb) | |||
| 22 | (n,na) | ( E-thr = 6.397 MeV ) | 9.980 (mb) | 2.649 (μb) | |||
| 28 | (n,np) | ( E-thr = 9.694 MeV ) | 134.5 (mb) | 25.90 (μb) | |||
| 102 | (n,γ) | 2.901 (b) | 2.902 (b) | 1.000 | 1.463 (b) | 69.65 (μb) | 6.359 (mb) |
| 103 | (n,p) | ( E-thr = 2.076 MeV ) | 157.7 (mb) | 2.202 (mb) | |||
| 104 | (n,d) | ( E-thr = 7.431 MeV ) | 3.878 (mb) | 942.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.70 MeV ) | 646.7 (nb) | 2.302 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 9.333 MeV ) | 89.13 (nb) | 168.5e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 24.22 (mb) | 68.26 (mb) | 1.623 (mb) |
| 111 | (n,2p) | ( E-thr = 10.49 MeV ) | 0.000 (b) | 933.6e-12 (b) | |||
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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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