50-Sn-117
Spin
Level energy(keV) Spin & Parity
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ground state 1/2+
3.14580E+02 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)
116.902953983 ± 0.000000519 (amu) [mass excess = -90397.782 ± 0.483 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1758.218 ± 8.445 (keV)
Strong Gamma-rays from Decay of Sn-117 (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
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156.02 2.11 IT
158.56 86.4 IT
314.3 4.E-04 IT
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*: 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 13.60 D 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-117.
Figures of cross sections, Sn-117: 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-116 (Z= 50, A=116), MT=102 (n,γ)
Sn-117 (Z= 50, A=117), MT= 2 (Elastic scattering)
Sn-117 (Z= 50, A=117), MT= 4 (Inelastic scattering)
Sn-118 (Z= 50, A=118), MT= 16 (n,2n)
Sn-119 (Z= 50, A=119), MT= 17 (n,3n)
Te-120 (Z= 52, A=120), MT=107 (n,α)
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)
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Sn-117 U-235 Thermal 1.165800e-13 7.461160e-14
Sn-117 U-235 Fast 1.330670e-13 8.516300e-14
Sn-117 U-235 High 2.575030e-10 1.648020e-10
Sn-117 U-238 High 7.235880e-13 4.630970e-13
Sn-117 Pu-239 Thermal 6.855110e-12 4.387270e-12
Sn-117 Pu-239 Fast 1.251710e-11 8.010940e-12
Sn-117 Pu-239 High 2.281080e-08 1.459890e-08
Sn-117 Pu-241 Thermal 4.423310e-15 2.830920e-15
Sn-117 Pu-241 Fast 6.745630e-14 4.317200e-14
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Sn-117m U-235 Thermal 3.816260e-13 2.442410e-13
Sn-117m U-235 Fast 5.036180e-13 3.223150e-13
Sn-117m U-235 High 1.595040e-09 1.020820e-09
Sn-117m U-238 High 4.482080e-12 2.868540e-12
Sn-117m Pu-239 Thermal 2.244020e-11 1.436180e-11
Sn-117m Pu-239 Fast 4.737330e-11 3.031890e-11
Sn-117m Pu-239 High 1.412960e-07 9.042920e-08
Sn-117m Pu-241 Thermal 1.447970e-14 9.267040e-15
Sn-117m Pu-241 Fast 2.553010e-13 1.633930e-13
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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)
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Sn-117 U-235 Thermal 1.273100e-04 8.147840e-05
Sn-117 U-235 Fast 3.669760e-04 2.348650e-04
Sn-117 U-235 High 1.063800e-02 6.808340e-03
Sn-117 U-238 Fast 3.744460e-04 2.875630e-06
Sn-117 U-238 High 6.011120e-03 3.847120e-03
Sn-117 Pu-239 Thermal 4.441720e-04 2.842700e-04
Sn-117 Pu-239 Fast 6.980880e-04 4.467770e-04
Sn-117 Pu-239 High 1.151260e-02 7.368040e-03
Sn-117 Pu-241 Thermal 2.354040e-04 1.506580e-04
Sn-117 Pu-241 Fast 8.772030e-04 5.614100e-04
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Sn-117m U-235 Thermal 1.157660e-06 7.409030e-07
Sn-117m U-235 Fast 3.301000e-06 2.112640e-06
Sn-117m U-235 High 9.620480e-05 6.157090e-05
Sn-117m U-238 Fast 3.354810e-06 2.147080e-06
Sn-117m U-238 High 5.386680e-05 3.447470e-05
Sn-117m Pu-239 Thermal 4.038380e-06 2.584560e-06
Sn-117m Pu-239 Fast 6.366540e-06 4.074570e-06
Sn-117m Pu-239 High 1.092780e-04 6.993810e-05
Sn-117m Pu-241 Thermal 2.108720e-06 1.349580e-06
Sn-117m Pu-241 Fast 7.863530e-06 5.032660e-06
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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