MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 9.040 (b) | 9.576 (b) | 1.059 | − | 4.638 (b) | 5.520 (b) |
2 | (n,elastic) | 4.017 (b) | 4.534 (b) | 1.129 | − | 2.929 (b) | 4.405 (b) |
4 | (n,inelastic) | ( E-thr = 334.8 keV ) | 241.9 (mb) | 992.9 (mb) | |||
16 | (n,2n) | ( E-thr = 8.785 MeV ) | 1.462 (b) | 1.716 (mb) | |||
17 | (n,3n) | ( E-thr = 15.31 MeV ) | − | 2.614 (μb) | |||
22 | (n,na) | ( E-thr = 4.871 MeV ) | 256.3 (nb) | 827.1e-12 (b) | |||
28 | (n,np) | ( E-thr = 7.365 MeV ) | 312.8 (μb) | 73.09 (nb) | |||
32 | (n,nd) | ( E-thr = 13.60 MeV ) | 0.000 (b) | 98.31e-12 (b) | |||
33 | (n,nt) | ( E-thr = 13.36 MeV ) | 0.000 (b) | 37.95e-12 (b) | |||
102 | (n,γ) | 5.002 (b) | 5.005 (b) | 1.001 | 55.86 (b) | 1.003 (mb) | 119.9 (mb) |
103 | (n,p) | ( E-thr = 1.580 MeV ) | 2.213 (mb) | 943.3 (nb) | |||
104 | (n,d) | ( E-thr = 5.036 MeV ) | 180.7 (μb) | 63.76 (nb) | |||
105 | (n,t) | ( E-thr = 7.364 MeV ) | 3.533 (μb) | 7.233 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 463.9 (nb) | 1.019 (mb) | 241.5 (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 :
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