MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 33.80 (b) | 34.70 (b) | 1.027 | − | 3.652 (b) | 4.984 (b) |
2 | (n,elastic) | 7.998 (b) | 9.026 (b) | 1.128 | − | 1.928 (b) | 4.003 (b) |
4 | (n,inelastic) | ( E-thr = 9.510 keV ) | 596.6 (mb) | 965.0 (mb) | |||
16 | (n,2n) | ( E-thr = 7.554 MeV ) | 1.108 (b) | 478.9 (μb) | |||
17 | (n,3n) | ( E-thr = 17.18 MeV ) | − | 9.111 (nb) | |||
22 | (n,na) | ( E-thr = 4.449 MeV ) | 29.13 (μb) | 11.78 (nb) | |||
28 | (n,np) | ( E-thr = 8.340 MeV ) | 1.901 (mb) | 555.2 (nb) | |||
32 | (n,nd) | ( E-thr = 15.33 MeV ) | − | 1.636e-12 (b) | |||
102 | (n,γ) | 25.80 (b) | 25.67 (b) | 0.995 | 46.50 (b) | 779.5 (μb) | 14.83 (mb) |
103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 1.759 (mb) | 16.78 (mb) | 159.0 (μb) |
104 | (n,d) | ( E-thr = 6.087 MeV ) | 619.2 (μb) | 142.9 (nb) | |||
105 | (n,t) | ( E-thr = 8.993 MeV ) | 743.0 (nb) | 500.3e-12 (b) | |||
106 | (n,He-3) | ( E-thr = 5.862 MeV ) | 322.3e-12 (b) | 394.6e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 95.87 (μb) | 671.6 (μb) | 6.429 (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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