52-Te-125
Spin
Level energy(keV) Spin & Parity
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ground state 1/2+
1.44780E+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)
124.904429920 ± 0.000001614 (amu) [mass excess = -89022.955 ± 1.504 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-185.770 ± 0.060 (keV)
Strong Gamma-rays from Decay of Te-125 (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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35.50 7.3 IT
109.28 0.28 IT
144.78 4.E-07 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 57.40 D 15
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Te-125.
Figures of cross sections, Te-125: 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
Te-124 (Z= 52, A=124), MT=102 (n,γ)
Te-125 (Z= 52, A=125), MT= 2 (Elastic scattering)
Te-125 (Z= 52, A=125), MT= 4 (Inelastic scattering)
Te-126 (Z= 52, A=126), MT= 16 (n,2n)
Te-127 (Z= 52, A=127), MT= 17 (n,3n)
I -127 (Z= 53, A=127), MT= 32 (n,nd)
I -127 (Z= 53, A=127), MT=105 (n,t)
Xe-128 (Z= 54, A=128), MT=107 (n,α)
Xe-129 (Z= 54, A=129), 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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Te-125 U-235 Thermal 6.980810e-14 4.467720e-14
Te-125 U-235 Fast 1.069960e-13 6.847750e-14
Te-125 U-235 High 3.755370e-07 2.403440e-07
Te-125 U-238 Fast 5.346120e-10 3.421510e-10
Te-125 U-238 High 3.899030e-09 2.495370e-09
Te-125 Pu-239 Thermal 1.452910e-11 9.298640e-12
Te-125 Pu-239 Fast 1.634110e-11 1.045830e-11
Te-125 Pu-239 High 8.769640e-06 5.612570e-06
Te-125 Pu-241 Thermal 7.840270e-14 5.017780e-14
Te-125 Pu-241 Fast 9.832330e-13 6.292690e-13
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Te-125m U-235 Thermal 2.285170e-13 1.462510e-13
Te-125m U-235 Fast 4.049470e-13 2.591660e-13
Te-125m U-235 High 2.326170e-06 1.488740e-06
Te-125m U-238 Fast 2.023340e-09 1.294940e-09
Te-125m U-238 High 2.415150e-08 1.545700e-08
Te-125m Pu-239 Thermal 4.756110e-11 3.043910e-11
Te-125m Pu-239 Fast 6.184620e-11 3.958150e-11
Te-125m Pu-239 High 5.432130e-05 3.476560e-05
Te-125m Pu-241 Thermal 2.566520e-13 1.642570e-13
Te-125m Pu-241 Fast 3.721230e-12 2.381590e-12
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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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Te-125 U-235 Thermal 3.396640e-04 6.824720e-06
Te-125 U-235 Fast 6.788980e-04 4.084150e-05
Te-125 U-235 High 1.462350e-02 1.168440e-03
Te-125 U-238 Fast 4.853520e-04 2.911480e-05
Te-125 U-238 High 1.196600e-02 4.785390e-04
Te-125 Pu-239 Thermal 1.116410e-03 8.932630e-05
Te-125 Pu-239 Fast 1.778170e-03 1.422740e-04
Te-125 Pu-239 High 1.956130e-02 1.563960e-03
Te-125 Pu-241 Thermal 4.690910e-04 3.752090e-05
Te-125 Pu-241 Fast 1.510010e-03 1.662320e-04
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Te-125m U-235 Thermal 1.188820e-04 4.239190e-05
Te-125m U-235 Fast 2.376140e-04 8.542740e-05
Te-125m U-235 High 5.119600e-03 1.906150e-03
Te-125m U-238 Fast 1.698740e-04 6.131860e-05
Te-125m U-238 High 4.188100e-03 1.505030e-03
Te-125m Pu-239 Thermal 3.907430e-04 1.409560e-04
Te-125m Pu-239 Fast 6.223600e-04 2.265340e-04
Te-125m Pu-239 High 6.878620e-03 2.488410e-03
Te-125m Pu-241 Thermal 1.641820e-04 5.978960e-05
Te-125m Pu-241 Fast 5.285050e-04 2.427780e-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