50-Sn-126
Spin
Level energy(keV) Spin & Parity
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ground state 0+
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)
125.907658786 ± 0.000011215 (amu) [mass excess = -86015.286 ± 10.447 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
378.000 ± 30.000 (keV)
Strong Gamma-rays from Decay of Sn-126 (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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64.28 9.62 B-
86.94 8.92 B-
87.57 37. B-
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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
B- 2.30E+5 Y 14
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-126.
Figures of cross sections, Sn-126: 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-126 (Z= 50, A=126), MT= 2 (Elastic scattering)
Sn-126 (Z= 50, A=126), MT= 4 (Inelastic scattering)
Sb-126 (Z= 51, A=126), MT=103 (n,p)
Te-129 (Z= 52, A=129), MT=107 (n,α)
Te-130 (Z= 52, A=130), 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)
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Sn-126 U-235 Thermal 4.440230e-04 2.841750e-04
Sn-126 U-235 Fast 6.773720e-04 4.335180e-04
Sn-126 U-235 High 9.307700e-03 2.978460e-03
Sn-126 U-238 Fast 1.626010e-04 1.040640e-04
Sn-126 U-238 High 3.276010e-03 2.096650e-03
Sn-126 Pu-239 Thermal 1.690000e-03 2.704010e-04
Sn-126 Pu-239 Fast 2.231840e-03 3.570940e-04
Sn-126 Pu-239 High 1.396770e-02 3.212560e-03
Sn-126 Pu-241 Thermal 4.914500e-04 3.145280e-04
Sn-126 Pu-241 Fast 1.615540e-03 5.169710e-04
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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-126 U-235 Thermal 5.582160e-04 4.502930e-05
Sn-126 U-235 Fast 9.701450e-04 1.558050e-04
Sn-126 U-235 High 1.703770e-02 1.362030e-03
Sn-126 U-238 Fast 5.394600e-04 4.327630e-05
Sn-126 U-238 High 1.314560e-02 2.104200e-03
Sn-126 Pu-239 Thermal 1.984840e-03 1.588910e-04
Sn-126 Pu-239 Fast 2.632410e-03 2.106970e-04
Sn-126 Pu-239 High 1.969610e-02 2.166050e-03
Sn-126 Pu-241 Thermal 8.192150e-04 1.886110e-04
Sn-126 Pu-241 Fast 2.223520e-03 3.562300e-04
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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