| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 11.31 (b) | 12.44 (b) | 1.100 | − | 2.814 (b) | 3.813 (b) |
| 2 | (n,elastic) | 8.804 (b) | 9.935 (b) | 1.128 | − | 1.470 (b) | 2.721 (b) |
| 4 | (n,inelastic) | ( E-thr = 68.52 keV ) | 282.9 (mb) | 1.079 (b) | |||
| 16 | (n,2n) | ( E-thr = 7.955 MeV ) | 928.4 (mb) | 1.753 (mb) | |||
| 22 | (n,na) | ( E-thr = 6.569 MeV ) | 2.914 (mb) | 718.5 (nb) | |||
| 28 | (n,np) | ( E-thr = 10.03 MeV ) | 11.16 (mb) | 2.234 (μb) | |||
| 102 | (n,γ) | 2.509 (b) | 2.509 (b) | 1.000 | 2.435 (b) | 18.35 (μb) | 5.458 (mb) |
| 103 | (n,p) | ( E-thr = 548.6 keV ) | 79.10 (mb) | 2.365 (mb) | |||
| 104 | (n,d) | ( E-thr = 7.681 MeV ) | 5.551 (mb) | 1.119 (μb) | |||
| 105 | (n,t) | ( E-thr = 9.014 MeV ) | 76.32 (μb) | 51.43 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 10.59 MeV ) | 453.5e-15 (b) | 77.07e-12 (b) | |||
| 107 | (n,a) | 538.3e-15 (b) | 1.215e-12 (b) | 2.257 | 20.94 (mb) | 33.45 (mb) | 2.562 (mb) |
| 111 | (n,2p) | ( E-thr = 9.447 MeV ) | 207.3 (nb) | 876.7e-12 (b) | |||
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These cross sections are calculated from JENDL-3.2 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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