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mcnp/U-234: U-234 T=300 K from ENDF/B-6.0 mat9225
Pick up 1 Total cross section
Pick up 101 (n, disappearance) Neutron disappearance XS. MT=101 is equal to the sum of MT=102-116.
Pick up 2 Elastic cross section
Pick up 301 Average heating number
Pick up 16 (z,2n) XS for producing two neutrons and a residual.
Pick up 17 (z,3n) XS for producing three neutrons and a residual.
Pick up 19 (n,f) First-chance fission XS.
Pick up 20 (n,nf) 2nd-chance fission XS.
Pick up 21 (n,2nf) 3rd-chance fission XS.
Pick up 51 (z,nl) XS to the first excited state of the residual nucleus.
Pick up 52 (z,n2) XS to the 2nd excited state of the residual nucleus.
Pick up 53 (z,n3) XS to the 3rd excited state of the residual nucleus.
Pick up 54 (z,n4) XS to the 4-th excited state of the residual nucleus.
Pick up 55 (z,n5) XS to the 5-th excited state of the residual nucleus.
Pick up 56 (z,n6) XS to the 6-th excited state of the residual nucleus.
Pick up 91 (z,nc) XS for the production of a single neutron in the continuum not included in the above discrete representation.
Pick up 102 (z,g) Radiative capture XS.