50-Sn-115
Spin
Level energy(keV) Spin & Parity
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ground state 1/2+
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)
114.903344699 ± 0.000000016 (amu) [mass excess = -90033.833 ± 0.015 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-3030.430 ± 16.025 (keV)
Strong Gamma-rays from Decay of Sn-115 (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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100.7 14.84 IT
115.9 53. IT
497.6 ~ 84.8 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(%). ]
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-115.
Figures of cross sections, Sn-115: 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-114 (Z= 50, A=114), MT=102 (n,γ)
Sn-115 (Z= 50, A=115), MT= 2 (Elastic scattering)
Sn-115 (Z= 50, A=115), MT= 4 (Inelastic scattering)
Sn-116 (Z= 50, A=116), MT= 16 (n,2n)
Sn-117 (Z= 50, A=117), MT= 17 (n,3n)
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-115 U-235 High 1.602200e-12 1.025400e-12
Sn-115 Pu-239 High 1.010660e-09 6.468190e-10
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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-115 U-235 Thermal 1.256070e-04 2.235610e-07
Sn-115 U-235 Fast 3.379690e-04 8.084460e-07
Sn-115 U-235 High 1.093330e-02 3.061570e-04
Sn-115 U-238 Fast 3.757070e-04 2.245360e-07
Sn-115 U-238 High 8.578670e-03 8.192840e-06
Sn-115 Pu-239 Thermal 4.258020e-04 1.925510e-07
Sn-115 Pu-239 Fast 8.136190e-04 4.573380e-07
Sn-115 Pu-239 High 1.272400e-02 7.630650e-04
Sn-115 Pu-241 Thermal 3.807720e-04 9.767250e-08
Sn-115 Pu-241 Fast 1.089000e-03 1.200940e-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