| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 18.84 (b) | 19.78 (b) | 1.050 | − | 3.842 (b) | 4.932 (b) |
| 2 | (n,elastic) | 7.337 (b) | 8.277 (b) | 1.128 | − | 2.543 (b) | 3.947 (b) |
| 4 | (n,inelastic) | ( E-thr = 624.4 keV ) | 441.4 (mb) | 899.4 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.68 MeV ) | 735.2 (mb) | 112.4 (μb) | |||
| 22 | (n,na) | ( E-thr = 5.124 MeV ) | 7.418 (mb) | 1.960 (μb) | |||
| 28 | (n,np) | ( E-thr = 9.236 MeV ) | 33.77 (mb) | 6.209 (μb) | |||
| 102 | (n,γ) | 11.50 (b) | 11.50 (b) | 1.000 | 60.18 (b) | 2.361 (mb) | 82.86 (mb) |
| 103 | (n,p) | ( E-thr = 1.239 MeV ) | 59.51 (mb) | 1.186 (mb) | |||
| 104 | (n,d) | ( E-thr = 6.896 MeV ) | 315.6 (μb) | 95.47 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.46 MeV ) | 4.774 (nb) | 1.335 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 7.819 MeV ) | 3.849 (nb) | 17.68e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 3.772 (mb) | 18.76 (mb) | 185.5 (μb) |
| 111 | (n,2p) | ( E-thr = 8.595 MeV ) | 449.0 (nb) | 1.955 (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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