| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 59.14 (b) | 60.11 (b) | 1.016 | − | 3.840 (b) | 4.941 (b) |
| 2 | (n,elastic) | 7.325 (b) | 8.258 (b) | 1.127 | − | 2.391 (b) | 3.878 (b) |
| 4 | (n,inelastic) | ( E-thr = 643.5 keV ) | 498.4 (mb) | 1.002 (b) | |||
| 16 | (n,2n) | ( E-thr = 12.24 MeV ) | 271.8 (mb) | 34.44 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.129 MeV ) | 174.3 (mb) | 50.20 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.674 MeV ) | 310.1 (mb) | 59.24 (μb) | |||
| 102 | (n,γ) | 51.82 (b) | 51.85 (b) | 1.001 | 579.8 (b) | 1.042 (mb) | 38.55 (mb) |
| 103 | (n,p) | ( E-thr = 578.3 keV ) | 151.4 (mb) | 17.48 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.332 MeV ) | 1.240 (mb) | 387.4 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.00 MeV ) | 179.3 (nb) | 3.278 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 6.574 MeV ) | 279.6 (nb) | 337.2e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 50.82 (mb) | 41.42 (mb) | 4.225 (mb) |
| 111 | (n,2p) | ( E-thr = 7.532 MeV ) | 12.38 (μb) | 5.474 (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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