MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 19.43 (b) | 20.84 (b) | 1.073 | − | 5.419 (b) | 6.852 (b) |
2 | (n,elastic) | 11.03 (b) | 12.45 (b) | 1.128 | − | 2.151 (b) | 4.523 (b) |
4 | (n,inelastic) | ( E-thr = 82.54 keV ) | 1.379 (b) | 2.281 (b) | |||
16 | (n,2n) | ( E-thr = 8.025 MeV ) | 1.885 (b) | 3.680 (mb) | |||
17 | (n,3n) | ( E-thr = 13.94 MeV ) | 0.000 (b) | 9.992 (μb) | |||
22 | (n,na) | ( E-thr = 1.202 MeV ) | 26.43 (μb) | 15.91 (nb) | |||
28 | (n,np) | ( E-thr = 9.047 MeV ) | 366.9 (nb) | 17.40 (nb) | |||
32 | (n,nd) | ( E-thr = 14.32 MeV ) | − | 4.132e-12 (b) | |||
33 | (n,nt) | ( E-thr = 14.11 MeV ) | − | 688.8e-15 (b) | |||
102 | (n,γ) | 8.395 (b) | 8.390 (b) | 0.999 | 36.31 (b) | 1.069 (mb) | 44.14 (mb) |
103 | (n,p) | ( E-thr = 3.243 MeV ) | 1.680 (mb) | 427.7 (nb) | |||
104 | (n,d) | ( E-thr = 6.721 MeV ) | 90.97 (μb) | 77.72 (nb) | |||
105 | (n,t) | ( E-thr = 8.091 MeV ) | 6.578 (μb) | 19.11 (nb) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 581.5 (nb) | 600.6 (μb) | 155.0 (nb) |
These cross sections are calculated from JENDL-3.3 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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