MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 21.80 (b) | 22.32 (b) | 1.024 | − | 4.818 (b) | 5.692 (b) |
2 | (n,elastic) | 3.772 (b) | 4.258 (b) | 1.129 | − | 2.802 (b) | 3.990 (b) |
4 | (n,inelastic) | ( E-thr = 40.26 keV ) | 349.3 (mb) | 1.676 (b) | |||
16 | (n,2n) | ( E-thr = 6.551 MeV ) | 1.650 (b) | 6.862 (mb) | |||
17 | (n,3n) | ( E-thr = 15.46 MeV ) | − | 705.9 (nb) | |||
22 | (n,na) | ( E-thr = 2.982 MeV ) | 7.369 (μb) | 3.800 (nb) | |||
28 | (n,np) | ( E-thr = 7.274 MeV ) | 815.2 (μb) | 218.1 (nb) | |||
32 | (n,nd) | ( E-thr = 11.16 MeV ) | 0.000 (b) | 362.9e-12 (b) | |||
102 | (n,γ) | 18.01 (b) | 18.02 (b) | 1.001 | 118.6 (b) | 1.065 (mb) | 19.54 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 556.9 (μb) | 16.10 (mb) | 26.87 (μb) |
104 | (n,d) | ( E-thr = 5.032 MeV ) | 1.063 (mb) | 242.2 (nb) | |||
105 | (n,t) | ( E-thr = 4.856 MeV ) | 25.27 (μb) | 7.092 (nb) | |||
106 | (n,He-3) | ( E-thr = 9.255 MeV ) | 0.000 (b) | 62.73e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 16.88 (μb) | 858.0 (μb) | 952.5 (nb) |
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 :
|