51-Sb-126
Spin
Level energy(keV) Spin & Parity
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ground state (8-)
1.77000E+01 (5+)
4.04000E+01 (3-)
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)
125.907252987 ± 0.000034103 (amu) [mass excess = -86393.286 ± 31.767 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
3672.043 ± 31.787 (keV)
Strong Gamma-rays from Decay of Sb-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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17.7 5.E-05 IT
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414.7 83.27 B-
666.5 99.6 B-
695.0 99.6 B-
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414.5 85.67 B-
666.1 85.67 B-
694.8 82.25 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- 12.35 D 6
B- 19.15 M 8
IT 19.15 M 8
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sb-126.
Figures of cross sections, Sb-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
Sb-125 (Z= 51, A=125), MT=102 (n,γ)
Sb-126 (Z= 51, A=126), MT= 2 (Elastic scattering)
Sb-126 (Z= 51, A=126), MT= 4 (Inelastic scattering)
Te-126 (Z= 52, A=126), MT=103 (n,p)
Te-127 (Z= 52, A=127), MT= 28 (n,np)
Te-127 (Z= 52, A=127), MT=104 (n,d)
Te-128 (Z= 52, A=128), MT=105 (n,t)
I -129 (Z= 53, A=129), MT=107 (n,α)
I -130 (Z= 53, A=130), MT= 22 (n,nα)
Cs-133 (Z= 55, A=133), MT=108 (n,2α)
Cs-134 (Z= 55, A=134), MT= 29 (n,n2α)
Cs-135 (Z= 55, A=135), MT= 30 (n,2n2α)
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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Sb-126 U-235 Thermal 8.755060e-06 5.603240e-06
Sb-126 U-235 Fast 7.831770e-07 5.012340e-07
Sb-126 U-235 High 9.044700e-04 5.788610e-04
Sb-126 U-238 Fast 6.774600e-08 4.335750e-08
Sb-126 U-238 High 5.748240e-05 2.586700e-05
Sb-126 Pu-239 Thermal 1.373970e-05 8.793400e-06
Sb-126 Pu-239 Fast 1.423410e-05 9.109830e-06
Sb-126 Pu-239 High 3.132500e-03 2.004800e-03
Sb-126 Pu-241 Thermal 8.681600e-07 5.556230e-07
Sb-126 Pu-241 Fast 5.475260e-06 3.504170e-06
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Sb-126m U-235 Thermal 2.348860e-05 1.100850e-05
Sb-126m U-235 Fast 1.638820e-06 7.824530e-07
Sb-126m U-235 High 1.020100e-03 4.864670e-04
Sb-126m U-238 Fast 1.418320e-07 6.770370e-08
Sb-126m U-238 High 6.080650e-05 2.985140e-05
Sb-126m Pu-239 Thermal 3.509280e-05 1.674000e-05
Sb-126m Pu-239 Fast 2.979880e-05 1.422480e-05
Sb-126m Pu-239 High 3.527810e-03 1.683330e-03
Sb-126m Pu-241 Thermal 2.218340e-06 1.058020e-06
Sb-126m Pu-241 Fast 1.146200e-05 5.471580e-06
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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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Sb-126 U-235 Thermal 9.019370e-05 1.436980e-05
Sb-126 U-235 Fast 1.368330e-04 1.510080e-05
Sb-126 U-235 High 3.432570e-03 2.752660e-04
Sb-126 U-238 Fast 7.561200e-05 6.064730e-06
Sb-126 U-238 High 1.906380e-03 3.045760e-04
Sb-126 Pu-239 Thermal 2.965300e-04 2.365070e-05
Sb-126 Pu-239 Fast 3.869440e-04 3.088190e-05
Sb-126 Pu-239 High 6.383850e-03 2.802180e-03
Sb-126 Pu-241 Thermal 1.158690e-04 2.665290e-05
Sb-126 Pu-241 Fast 3.183730e-04 3.500660e-05
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Sb-126m U-235 Thermal 5.817040e-04 4.690910e-05
Sb-126m U-235 Fast 9.717840e-04 1.073260e-04
Sb-126m U-235 High 1.805780e-02 1.082700e-03
Sb-126m U-238 Fast 5.396020e-04 4.328830e-05
Sb-126m U-238 High 1.320640e-02 2.113910e-03
Sb-126m Pu-239 Thermal 2.019930e-03 1.616990e-04
Sb-126m Pu-239 Fast 2.662210e-03 2.130820e-04
Sb-126m Pu-239 High 2.322390e-02 3.714690e-03
Sb-126m Pu-241 Thermal 8.214330e-04 1.891180e-04
Sb-126m Pu-241 Fast 2.234980e-03 2.461790e-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