| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 3.323 (b) | 3.676 (b) | 1.106 | − | 2.399 (b) | 3.606 (b) |
| 2 | (n,elastic) | 2.733 (b) | 3.086 (b) | 1.129 | − | 954.4 (mb) | 2.927 (b) |
| 4 | (n,inelastic) | ( E-thr = 908.8 keV ) | 786.1 (mb) | 661.6 (mb) | |||
| 16 | (n,2n) | ( E-thr = 13.49 MeV ) | 12.64 (mb) | 3.845 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.189 MeV ) | 5.512 (mb) | 1.053 (μb) | |||
| 28 | (n,np) | ( E-thr = 10.58 MeV ) | 287.0 (mb) | 41.31 (μb) | |||
| 102 | (n,γ) | 589.7 (mb) | 590.1 (mb) | 1.001 | 366.1 (mb) | 363.9 (μb) | 4.644 (mb) |
| 103 | (n,p) | ( E-thr = 1.620 MeV ) | 259.0 (mb) | 13.10 (mb) | |||
| 104 | (n,d) | ( E-thr = 8.306 MeV ) | 1.660 (mb) | 363.0 (nb) | |||
| 105 | (n,t) | ( E-thr = 13.48 MeV ) | 0.000 (b) | 474.5e-12 (b) | |||
| 106 | (n,He-3) | ( E-thr = 9.731 MeV ) | 427.5 (nb) | 864.5e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 81.81 keV ) | 92.49 (mb) | 888.4 (μb) | |||
| 111 | (n,2p) | ( E-thr = 10.03 MeV ) | 254.5 (μb) | 151.0 (nb) | |||
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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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