MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.428 (b) | 6.111 (b) | 1.126 | − | 4.916 (b) | 6.064 (b) |
2 | (n,elastic) | 5.297 (b) | 5.981 (b) | 1.129 | − | 2.824 (b) | 5.137 (b) |
4 | (n,inelastic) | ( E-thr = 1.323 MeV ) | 311.1 (mb) | 922.6 (mb) | |||
16 | (n,2n) | ( E-thr = 8.139 MeV ) | 1.779 (b) | 2.757 (mb) | |||
17 | (n,3n) | ( E-thr = 14.55 MeV ) | − | 1.673 (μb) | |||
22 | (n,na) | ( E-thr = 3.695 MeV ) | 1.429 (μb) | 814.0e-12 (b) | |||
28 | (n,np) | ( E-thr = 9.998 MeV ) | 4.411 (μb) | 19.14 (nb) | |||
32 | (n,nd) | ( E-thr = 15.60 MeV ) | − | 293.5e-15 (b) | |||
102 | (n,γ) | 130.0 (mb) | 130.1 (mb) | 1.001 | 85.47 (mb) | 681.1 (μb) | 553.7 (μb) |
103 | (n,p) | ( E-thr = 6.189 MeV ) | 773.0 (μb) | 189.9 (nb) | |||
104 | (n,d) | ( E-thr = 7.757 MeV ) | 157.1 (μb) | 51.04 (nb) | |||
105 | (n,t) | ( E-thr = 9.300 MeV ) | 168.9 (nb) | 787.0e-12 (b) | |||
106 | (n,He-3) | ( E-thr = 10.81 MeV ) | 36.36e-21 (b) | 1.177e-15 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 2.407 (μb) | 113.4 (μb) | 115.9 (nb) |
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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