| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.936 (b) | 4.421 (b) | 1.123 | − | 2.510 (b) | 3.501 (b) |
| 2 | (n,elastic) | 3.757 (b) | 4.241 (b) | 1.129 | − | 1.008 (b) | 3.111 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.585 MeV ) | 653.8 (mb) | 390.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.17 MeV ) | 830.0 (mb) | 165.7 (μb) | |||
| 17 | (n,3n) | ( E-thr = 19.48 MeV ) | − | 59.46e-12 (b) | |||
| 22 | (n,na) | ( E-thr = 10.94 MeV ) | 8.519 (nb) | 2.800 (nb) | |||
| 28 | (n,np) | ( E-thr = 12.42 MeV ) | 56.51 (μb) | 164.1 (nb) | |||
| 102 | (n,γ) | 179.5 (mb) | 179.6 (mb) | 1.001 | 88.33 (mb) | 260.2 (μb) | 427.4 (μb) |
| 103 | (n,p) | ( E-thr = 6.229 MeV ) | 10.88 (mb) | 5.804 (μb) | |||
| 104 | (n,d) | ( E-thr = 10.15 MeV ) | 3.722 (μb) | 36.96 (nb) | |||
| 105 | (n,t) | ( E-thr = 14.10 MeV ) | − | 144.4e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 14.36 MeV ) | − | 227.8e-15 (b) | |||
| 107 | (n,a) | ( E-thr = 3.513 MeV ) | 7.232 (mb) | 3.310 (μb) | |||
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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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