50-Sn-123
Spin
Level energy(keV) Spin & Parity
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ground state 11/2-
2.46000E+01 3/2+
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)
122.905725221 ± 0.000002601 (amu) [mass excess = -87816.391 ± 2.423 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1408.435 ± 2.976 (keV)
Strong Gamma-rays from Decay of Sn-123 (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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160.32 85.7 B-
381.4 0.04 B-
541.8 0.02 B-
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160.33 2.E-03 B-
1030.23 0.03 B-
1088.64 0.6 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- 129.2 D 4
B- 40.06 M 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sn-123.
Figures of cross sections, Sn-123: 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-122 (Z= 50, A=122), MT=102 (n,γ)
Sn-123 (Z= 50, A=123), MT= 2 (Elastic scattering)
Sn-123 (Z= 50, A=123), MT= 4 (Inelastic scattering)
Sn-124 (Z= 50, A=124), MT= 16 (n,2n)
Sb-123 (Z= 51, A=123), MT=103 (n,p)
Sb-124 (Z= 51, A=124), MT= 28 (n,np)
Sb-124 (Z= 51, A=124), MT=104 (n,d)
Sb-125 (Z= 51, A=125), MT= 32 (n,nd)
Sb-125 (Z= 51, A=125), MT=105 (n,t)
Te-126 (Z= 52, A=126), MT=107 (n,α)
Te-127 (Z= 52, A=127), 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-123 U-235 Thermal 7.863460e-06 3.538550e-06
Sn-123 U-235 Fast 3.938510e-05 2.520640e-05
Sn-123 U-235 High 5.547210e-04 3.550210e-04
Sn-123 U-238 Fast 3.317740e-06 2.123350e-06
Sn-123 U-238 High 4.660140e-05 2.982490e-05
Sn-123 Pu-239 Thermal 1.033050e-04 6.611500e-05
Sn-123 Pu-239 Fast 1.992600e-04 1.275270e-04
Sn-123 Pu-239 High 2.710750e-03 1.734880e-03
Sn-123 Pu-241 Thermal 1.629190e-05 1.042680e-05
Sn-123 Pu-241 Fast 9.013370e-05 5.768550e-05
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Sn-123m U-235 Thermal 3.258830e-06 1.042830e-06
Sn-123m U-235 Fast 1.405470e-05 8.994960e-06
Sn-123m U-235 High 1.209440e-04 7.740440e-05
Sn-123m U-238 Fast 1.183940e-06 7.577210e-07
Sn-123m U-238 High 1.016040e-05 6.502660e-06
Sn-123m Pu-239 Thermal 4.281240e-05 2.739990e-05
Sn-123m Pu-239 Fast 7.110620e-05 4.550790e-05
Sn-123m Pu-239 High 5.910170e-04 3.782510e-04
Sn-123m Pu-241 Thermal 6.751810e-06 4.321170e-06
Sn-123m Pu-241 Fast 3.216440e-05 2.058520e-05
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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)
-----------------------------------------------------------
Sn-123 U-235 Thermal 9.971380e-06 4.117340e-06
Sn-123 U-235 Fast 4.707350e-05 2.637900e-05
Sn-123 U-235 High 7.642660e-04 4.122150e-04
Sn-123 U-238 Fast 9.653150e-06 6.178010e-06
Sn-123 U-238 High 1.704080e-04 1.090610e-04
Sn-123 Pu-239 Thermal 1.100400e-04 6.646520e-05
Sn-123 Pu-239 Fast 2.108590e-04 1.280690e-04
Sn-123 Pu-239 High 3.023160e-03 1.761990e-03
Sn-123 Pu-241 Thermal 2.101140e-05 1.144470e-05
Sn-123 Pu-241 Fast 1.083570e-04 6.051660e-05
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Sn-123m U-235 Thermal 1.463530e-04 6.367980e-06
Sn-123m U-235 Fast 3.923420e-04 9.259050e-05
Sn-123m U-235 High 1.117160e-02 2.620310e-03
Sn-123m U-238 Fast 4.359410e-04 1.415790e-04
Sn-123m U-238 High 9.065530e-03 2.112110e-03
Sn-123m Pu-239 Thermal 3.264650e-04 1.501180e-04
Sn-123m Pu-239 Fast 5.484090e-04 2.523100e-04
Sn-123m Pu-239 High 1.412080e-02 4.625360e-03
Sn-123m Pu-241 Thermal 2.459340e-04 1.128720e-04
Sn-123m Pu-241 Fast 9.075880e-04 2.970860e-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