| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 14.08 (b) | 15.09 (b) | 1.072 | − | 3.841 (b) | 4.932 (b) |
| 2 | (n,elastic) | 7.881 (b) | 8.892 (b) | 1.128 | − | 2.644 (b) | 3.792 (b) |
| 4 | (n,inelastic) | ( E-thr = 460.9 keV ) | 409.8 (mb) | 1.057 (b) | |||
| 16 | (n,2n) | ( E-thr = 12.15 MeV ) | 192.4 (mb) | 24.50 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.416 MeV ) | 30.79 (mb) | 6.986 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.308 MeV ) | 361.0 (mb) | 73.94 (μb) | |||
| 102 | (n,γ) | 6.202 (b) | 6.201 (b) | 1.000 | 25.73 (b) | 1.117 (mb) | 67.31 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 124.5 (mb) | 156.5 (mb) | 11.48 (mb) |
| 104 | (n,d) | ( E-thr = 5.968 MeV ) | 847.7 (μb) | 282.2 (nb) | |||
| 105 | (n,t) | ( E-thr = 10.86 MeV ) | 192.0 (nb) | 3.563 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 5.821 MeV ) | 151.2 (nb) | 236.0e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 30.14 (mb) | 43.15 (mb) | 2.396 (mb) |
| 111 | (n,2p) | ( E-thr = 6.133 MeV ) | 1.402 (mb) | 312.3 (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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