50-Sn-119
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 1/2+
8.95350E+01 11/2-
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
118.903311172 ± 0.000000779 (amu) [mass excess = -90065.063 ± 0.726 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-590.846 ± 7.689 (keV)
Strong Gamma-rays from Decay of Sn-119 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
----------------------------------------------------------
23.88 16.5 IT
65.66 0.02 IT
----------------------------------------------------------
*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
IT 293 D 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-119.
Figures of cross sections, Sn-119: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Sn-118 (Z= 50, A=118), MT=102 (n,γ)
Sn-119 (Z= 50, A=119), MT= 2 (Elastic scattering)
Sn-119 (Z= 50, A=119), MT= 4 (Inelastic scattering)
Sn-120 (Z= 50, A=120), MT= 16 (n,2n)
Sb-121 (Z= 51, A=121), MT=105 (n,t)
Te-122 (Z= 52, A=122), MT=107 (n,α)
Te-123 (Z= 52, A=123), MT= 22 (n,nα)
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
-----------------------------------------------------------
Sn-119 U-235 Thermal 3.457700e-10 2.212930e-10
Sn-119 U-235 Fast 6.839000e-10 4.376960e-10
Sn-119 U-235 High 6.457060e-08 4.132520e-08
Sn-119 U-238 Fast 5.030410e-12 3.219460e-12
Sn-119 U-238 High 5.258530e-10 3.365460e-10
Sn-119 Pu-239 Thermal 1.118340e-08 7.157370e-09
Sn-119 Pu-239 Fast 1.901590e-08 1.217020e-08
Sn-119 Pu-239 High 1.858250e-06 1.189280e-06
Sn-119 Pu-241 Thermal 9.785120e-11 6.262490e-11
Sn-119 Pu-241 Fast 5.208540e-10 3.333470e-10
-----------------------------------------------------------
Sn-119m U-235 Thermal 1.131880e-09 7.244010e-10
Sn-119m U-235 Fast 2.588350e-09 1.656550e-09
Sn-119m U-235 High 3.999660e-07 2.559780e-07
Sn-119m U-238 Fast 1.903850e-11 1.218470e-11
Sn-119m U-238 High 3.257260e-09 2.084650e-09
Sn-119m Pu-239 Thermal 3.660900e-08 2.342980e-08
Sn-119m Pu-239 Fast 7.196930e-08 4.606040e-08
Sn-119m Pu-239 High 1.151040e-05 7.366670e-06
Sn-119m Pu-241 Thermal 3.203160e-10 2.050030e-10
Sn-119m Pu-241 Fast 1.971270e-09 1.261610e-09
-----------------------------------------------------------
Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
-----------------------------------------------------------
Sn-119 U-235 Thermal 1.285440e-04 1.030020e-05
Sn-119 U-235 Fast 3.494760e-04 2.802510e-05
Sn-119 U-235 High 1.085630e-02 1.192530e-03
Sn-119 U-238 Fast 3.973530e-04 4.369260e-05
Sn-119 U-238 High 7.267400e-03 7.985890e-04
Sn-119 Pu-239 Thermal 3.224490e-04 2.579890e-05
Sn-119 Pu-239 Fast 5.500940e-04 6.051760e-05
Sn-119 Pu-239 High 1.252670e-02 1.377060e-03
Sn-119 Pu-241 Thermal 2.316060e-04 7.409910e-05
Sn-119 Pu-241 Fast 8.232680e-04 1.318230e-04
-----------------------------------------------------------
Sn-119m U-235 Thermal 6.688250e-07 1.538300e-07
Sn-119m U-235 Fast 1.753770e-06 7.891970e-07
Sn-119m U-235 High 5.115350e-05 1.636920e-05
Sn-119m U-238 Fast 1.508440e-06 6.787950e-07
Sn-119m U-238 High 2.822530e-05 1.270140e-05
Sn-119m Pu-239 Thermal 1.834180e-06 8.253810e-07
Sn-119m Pu-239 Fast 3.245220e-06 1.460350e-06
Sn-119m Pu-239 High 8.588850e-05 2.748430e-05
Sn-119m Pu-241 Thermal 1.001410e-06 4.506340e-07
Sn-119m Pu-241 Fast 3.669490e-06 1.651270e-06
-----------------------------------------------------------
Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data