MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 13.77 (b) | 14.53 (b) | 1.055 | − | 4.340 (b) | 5.671 (b) |
2 | (n,elastic) | 5.730 (b) | 6.466 (b) | 1.128 | − | 2.832 (b) | 3.951 (b) |
4 | (n,inelastic) | ( E-thr = 99.00 keV ) | 69.42 (mb) | 1.665 (b) | |||
16 | (n,2n) | ( E-thr = 5.991 MeV ) | 1.429 (b) | 19.54 (mb) | |||
17 | (n,3n) | ( E-thr = 14.73 MeV ) | − | 4.293 (μb) | |||
22 | (n,na) | ( E-thr = 2.756 MeV ) | 187.6 (μb) | 45.16 (nb) | |||
28 | (n,np) | ( E-thr = 9.832 MeV ) | 23.39 (μb) | 23.04 (nb) | |||
32 | (n,nd) | ( E-thr = 13.55 MeV ) | 0.000 (b) | 315.3e-12 (b) | |||
33 | (n,nt) | ( E-thr = 15.47 MeV ) | − | 1.128e-12 (b) | |||
102 | (n,γ) | 8.003 (b) | 8.003 (b) | 1.000 | 41.57 (b) | 1.001 (mb) | 34.38 (mb) |
103 | (n,p) | ( E-thr = 2.870 MeV ) | 6.708 (mb) | 2.657 (μb) | |||
104 | (n,d) | ( E-thr = 7.499 MeV ) | 267.8 (μb) | 64.34 (nb) | |||
105 | (n,t) | ( E-thr = 7.306 MeV ) | 20.41 (μb) | 10.83 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 63.65 (μb) | 1.950 (mb) | 6.850 (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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