MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.287 (b) | 5.962 (b) | 1.128 | − | 1.414 (b) | 2.426 (b) |
2 | (n,elastic) | 5.281 (b) | 5.957 (b) | 1.128 | − | 934.9 (mb) | 2.397 (b) |
4 | (n,inelastic) | ( E-thr = 2.320 MeV ) | 298.3 (mb) | 28.81 (mb) | |||
16 | (n,2n) | ( E-thr = 12.51 MeV ) | 1.414 (mb) | 496.7 (nb) | |||
22 | (n,na) | ( E-thr = 9.460 MeV ) | 101.0 (mb) | 27.54 (μb) | |||
28 | (n,np) | ( E-thr = 12.26 MeV ) | 1.104 (mb) | 211.0 (nb) | |||
29 | (n,n2a) | ( E-thr = 12.15 MeV ) | 17.96 (mb) | 3.696 (μb) | |||
32 | (n,nd) | ( E-thr = 17.27 MeV ) | − | 1.335 (nb) | |||
33 | (n,nt) | ( E-thr = 12.25 MeV ) | 747.4 (μb) | 169.9 (nb) | |||
102 | (n,γ) | 5.075 (mb) | 5.080 (mb) | 1.001 | 2.543 (mb) | 0.000 (b) | 5.473 (μb) |
103 | (n,p) | ( E-thr = 11.71 MeV ) | 4.021 (mb) | 579.7 (nb) | |||
104 | (n,d) | ( E-thr = 9.830 MeV ) | 9.200 (mb) | 4.074 (μb) | |||
105 | (n,t) | ( E-thr = 10.44 MeV ) | 14.96 (mb) | 3.443 (μb) | |||
107 | (n,a) | ( E-thr = 7.240 MeV ) | 31.38 (mb) | 63.13 (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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