| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 9.035 (b) | 10.03 (b) | 1.110 | − | 4.336 (b) | 5.653 (b) |
| 2 | (n,elastic) | 7.757 (b) | 8.753 (b) | 1.128 | − | 2.725 (b) | 5.036 (b) |
| 4 | (n,inelastic) | ( E-thr = 919.4 keV ) | 577.5 (mb) | 608.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 11.60 MeV ) | 847.5 (mb) | 133.5 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.049 MeV ) | 1.018 (μb) | 29.88 (nb) | |||
| 28 | (n,np) | ( E-thr = 7.159 MeV ) | 152.3 (mb) | 88.26 (μb) | |||
| 32 | (n,nd) | ( E-thr = 16.07 MeV ) | − | 15.75e-12 (b) | |||
| 102 | (n,γ) | 1.278 (b) | 1.278 (b) | 1.000 | 867.4 (mb) | 1.058 (mb) | 6.260 (mb) |
| 103 | (n,p) | ( E-thr = 717.9 keV ) | 25.93 (mb) | 204.4 (μb) | |||
| 104 | (n,d) | ( E-thr = 4.822 MeV ) | 1.871 (mb) | 445.9 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.811 MeV ) | 610.0 (nb) | 3.241 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 10.07 MeV ) | 137.6e-15 (b) | 6.034e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 48.44 (μb) | 4.482 (mb) | 2.756 (μb) |
|
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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