MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 5.407 (b) | 6.100 (b) | 1.128 | − | 3.846 (b) | 5.688 (b) |
2 | (n,elastic) | 5.396 (b) | 6.089 (b) | 1.128 | − | 2.183 (b) | 5.201 (b) |
4 | (n,inelastic) | ( E-thr = 1.780 MeV ) | 925.7 (mb) | 480.1 (mb) | |||
16 | (n,2n) | ( E-thr = 12.12 MeV ) | 611.3 (mb) | 83.00 (μb) | |||
22 | (n,na) | ( E-thr = 6.749 MeV ) | 21.13 (μb) | 36.70 (nb) | |||
28 | (n,np) | ( E-thr = 8.457 MeV ) | 74.46 (mb) | 16.94 (μb) | |||
32 | (n,nd) | ( E-thr = 17.81 MeV ) | − | 499.4e-15 (b) | |||
102 | (n,γ) | 11.13 (mb) | 11.13 (mb) | 1.000 | 168.1 (mb) | 1.030 (mb) | 6.304 (mb) |
103 | (n,p) | ( E-thr = 1.518 MeV ) | 41.04 (mb) | 174.5 (μb) | |||
104 | (n,d) | ( E-thr = 6.121 MeV ) | 1.120 (mb) | 243.3 (nb) | |||
105 | (n,t) | ( E-thr = 11.47 MeV ) | 1.548 (nb) | 1.729 (nb) | |||
106 | (n,He-3) | ( E-thr = 7.796 MeV ) | 377.1e-12 (b) | 28.18e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 262.6 (μb) | 8.385 (mb) | 11.51 (μb) |
111 | (n,2p) | ( E-thr = 9.175 MeV ) | 251.5e-12 (b) | 28.61e-12 (b) |
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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