| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.268 (b) | 8.147 (b) | 1.121 | − | 3.271 (b) | 4.207 (b) |
| 2 | (n,elastic) | 6.847 (b) | 7.727 (b) | 1.128 | − | 1.694 (b) | 3.377 (b) |
| 4 | (n,inelastic) | ( E-thr = 604.0 keV ) | 472.2 (mb) | 822.7 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.34 MeV ) | 1.076 (b) | 423.2 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.21 MeV ) | − | 47.20 (nb) | |||
| 22 | (n,na) | ( E-thr = 6.373 MeV ) | 315.7 (μb) | 122.2 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.12 MeV ) | 212.5 (μb) | 175.7 (nb) | |||
| 102 | (n,γ) | 420.1 (mb) | 420.1 (mb) | 1.000 | 455.2 (mb) | 771.5 (μb) | 5.956 (mb) |
| 103 | (n,p) | ( E-thr = 4.784 MeV ) | 9.900 (mb) | 9.012 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.865 MeV ) | 1.251 (mb) | 260.5 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.87 MeV ) | 1.620 (nb) | 411.3e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 449.6 keV ) | 15.77 (mb) | 19.84 (μb) | |||
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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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