MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
---|---|---|---|---|---|---|---|
1 | (n,total) | 9.680 (b) | 10.38 (b) | 1.073 | − | 4.722 (b) | 5.938 (b) |
2 | (n,elastic) | 5.407 (b) | 6.104 (b) | 1.129 | − | 2.541 (b) | 4.103 (b) |
4 | (n,inelastic) | ( E-thr = 391.7 keV ) | 663.4 (mb) | 1.689 (b) | |||
16 | (n,2n) | ( E-thr = 10.13 MeV ) | 1.473 (b) | 542.6 (μb) | |||
17 | (n,3n) | ( E-thr = 17.79 MeV ) | − | 19.96 (nb) | |||
22 | (n,na) | ( E-thr = 1.290 MeV ) | 573.9 (μb) | 320.2 (nb) | |||
28 | (n,np) | ( E-thr = 7.682 MeV ) | 4.167 (mb) | 944.7 (nb) | |||
32 | (n,nd) | ( E-thr = 15.06 MeV ) | − | 1.001e-12 (b) | |||
102 | (n,γ) | 4.273 (b) | 4.279 (b) | 1.001 | 65.58 (b) | 1.302 (mb) | 145.3 (mb) |
103 | (n,p) | ( E-thr = 479.5 keV ) | 38.14 (mb) | 165.4 (μb) | |||
104 | (n,d) | ( E-thr = 5.440 MeV ) | 674.2 (μb) | 157.9 (nb) | |||
105 | (n,t) | ( E-thr = 8.752 MeV ) | 915.1 (nb) | 2.051 (nb) | |||
106 | (n,He-3) | ( E-thr = 5.548 MeV ) | 244.3e-12 (b) | 1.407e-12 (b) | |||
107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 283.0 (μb) | 3.677 (mb) | 28.18 (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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