MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 24.87 (kb) | 25.90 (kb) | 1.042 | − | 4.535 (b) | 5.614 (b) |
2 | (n,elastic) | 9.032 (kb) | 10.11 (kb) | 1.119 | − | 2.827 (b) | 4.038 (b) |
4 | (n,inelastic) | ( E-thr = 130.8 keV ) | 213.3 (mb) | 1.493 (b) | |||
16 | (n,2n) | ( E-thr = 9.065 MeV ) | 1.473 (b) | 1.551 (mb) | |||
17 | (n,3n) | ( E-thr = 16.14 MeV ) | − | 1.155 (μb) | |||
22 | (n,na) | ( E-thr = 3.988 MeV ) | 146.8 (μb) | 43.73 (nb) | |||
28 | (n,np) | ( E-thr = 7.117 MeV ) | 4.405 (mb) | 935.6 (nb) | |||
32 | (n,nd) | ( E-thr = 13.78 MeV ) | 0.000 (b) | 315.0e-12 (b) | |||
33 | (n,nt) | ( E-thr = 13.84 MeV ) | 0.000 (b) | 78.13e-12 (b) | |||
102 | (n,γ) | 15.83 (kb) | 15.79 (kb) | 0.997 | 17.00 (kb) | 1.012 (mb) | 78.04 (mb) |
103 | (n,p) | ( E-thr = 1.145 MeV ) | 12.56 (mb) | 23.03 (μb) | |||
104 | (n,d) | ( E-thr = 4.785 MeV ) | 423.5 (μb) | 109.6 (nb) | |||
105 | (n,t) | ( E-thr = 7.540 MeV ) | 13.49 (μb) | 14.23 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 25.95 (μb) | 2.761 (mb) | 1.644 (μb) |
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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