| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.748 (b) | 5.358 (b) | 1.128 | − | 1.643 (b) | 2.684 (b) |
| 2 | (n,elastic) | 4.748 (b) | 5.357 (b) | 1.128 | − | 1.080 (b) | 2.678 (b) |
| 4 | (n,inelastic) | ( E-thr = 5.625 MeV ) | 329.3 (mb) | 5.895 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.56 MeV ) | 62.72 (mb) | 9.942 (μb) | |||
| 22 | (n,na) | ( E-thr = 11.73 MeV ) | 7.976 (mb) | 1.804 (μb) | |||
| 28 | (n,np) | ( E-thr = 10.89 MeV ) | 37.00 (mb) | 8.488 (μb) | |||
| 32 | (n,nd) | ( E-thr = 17.25 MeV ) | − | 3.194 (nb) | |||
| 33 | (n,nt) | ( E-thr = 15.85 MeV ) | − | 20.82 (nb) | |||
| 102 | (n,γ) | 24.26 (μb) | 24.29 (μb) | 1.001 | 95.66 (μb) | 14.83 (μb) | 15.86 (μb) |
| 103 | (n,p) | ( E-thr = 9.594 MeV ) | 25.87 (mb) | 14.34 (μb) | |||
| 104 | (n,d) | ( E-thr = 8.520 MeV ) | 15.14 (mb) | 37.19 (μb) | |||
| 105 | (n,t) | ( E-thr = 10.57 MeV ) | 25.53 (mb) | 6.715 (μb) | |||
| 107 | (n,a) | ( E-thr = 8.134 MeV ) | 60.09 (mb) | 49.78 (μb) | |||
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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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