| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 15.53 (b) | 17.14 (b) | 1.104 | − | 3.084 (b) | 4.115 (b) |
| 2 | (n,elastic) | 12.59 (b) | 14.21 (b) | 1.128 | − | 1.603 (b) | 3.473 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.054 MeV ) | 791.2 (mb) | 604.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.70 MeV ) | 407.1 (mb) | 60.64 (μb) | |||
| 22 | (n,na) | ( E-thr = 4.148 MeV ) | 97.68 (mb) | 62.14 (μb) | |||
| 28 | (n,np) | ( E-thr = 8.648 MeV ) | 41.89 (mb) | 11.76 (μb) | |||
| 102 | (n,γ) | 2.936 (b) | 2.935 (b) | 1.000 | 2.506 (b) | 777.7 (μb) | 29.02 (mb) |
| 103 | (n,p) | ( E-thr = 883.5 keV ) | 104.1 (mb) | 5.777 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.391 MeV ) | 6.539 (mb) | 2.088 (μb) | |||
| 105 | (n,t) | ( E-thr = 10.50 MeV ) | 10.21 (μb) | 13.56 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 7.521 MeV ) | 513.9 (nb) | 376.4e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 18.01 (mb) | 31.04 (mb) | 2.072 (mb) |
| 111 | (n,2p) | ( E-thr = 8.774 MeV ) | 855.8 (nb) | 1.295 (nb) | |||
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These cross sections are calculated from JENDL-3.2 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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