52-Te-127
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 3/2+
8.82600E+01 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)
126.905225735 ± 0.000001627 (amu) [mass excess = -88281.659 ± 1.516 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
702.236 ± 3.576 (keV)
Strong Gamma-rays from Decay of Te-127 (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
----------------------------------------------------------
57.63 0.5 B-
593.3 2.E-03 B-
658.9 0.01 B-
88.26 0.08 IT
----------------------------------------------------------
202.9 0.06 B-
360.3 0.13 B-
417.9 0.99 B-
----------------------------------------------------------
*: 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- 9.35 H 7
B- 109 D 2
IT 109 D 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Te-127M.
Figures of cross sections, Te-127M: 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-126 (Z= 52, A=126), MT=102 (n,γ)
Te-127 (Z= 52, A=127), MT= 2 (Elastic scattering)
Te-127 (Z= 52, A=127), MT= 4 (Inelastic scattering)
Te-128 (Z= 52, A=128), MT= 16 (n,2n)
Te-129 (Z= 52, A=129), MT= 17 (n,3n)
I -127 (Z= 53, A=127), MT=103 (n,p)
I -129 (Z= 53, A=129), MT= 32 (n,nd)
I -129 (Z= 53, A=129), MT=105 (n,t)
Xe-129 (Z= 54, A=129), MT=106 (n,3He)
Xe-130 (Z= 54, A=130), MT=107 (n,α)
Xe-131 (Z= 54, A=131), 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)
-----------------------------------------------------------
Te-127 U-235 Thermal 1.001050e-10 6.406730e-11
Te-127 U-235 Fast 1.110200e-10 7.105270e-11
Te-127 U-235 High 3.311390e-05 2.119290e-05
Te-127 U-238 Fast 1.031350e-12 6.600590e-13
Te-127 U-238 High 1.103840e-06 7.064610e-07
Te-127 Pu-239 Thermal 7.429320e-09 4.754760e-09
Te-127 Pu-239 Fast 5.966500e-09 3.818560e-09
Te-127 Pu-239 High 1.083190e-04 6.932400e-05
Te-127 Pu-241 Thermal 1.655720e-10 1.059660e-10
Te-127 Pu-241 Fast 4.685770e-10 2.998890e-10
-----------------------------------------------------------
Te-127m U-235 Thermal 2.415510e-10 1.545920e-10
Te-127m U-235 Fast 3.111080e-10 1.991090e-10
Te-127m U-235 High 1.518800e-04 9.720300e-05
Te-127m U-238 Fast 2.890120e-12 1.849670e-12
Te-127m U-238 High 5.062870e-06 3.240230e-06
Te-127m Pu-239 Thermal 1.792670e-08 1.147310e-08
Te-127m Pu-239 Fast 1.671980e-08 1.070070e-08
Te-127m Pu-239 High 4.968140e-04 3.179610e-04
Te-127m Pu-241 Thermal 3.995200e-10 2.556930e-10
Te-127m Pu-241 Fast 1.313080e-09 8.403730e-10
-----------------------------------------------------------
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)
-----------------------------------------------------------
Te-127 U-235 Thermal 1.564420e-03 6.254800e-05
Te-127 U-235 Fast 3.047560e-03 8.548140e-05
Te-127 U-235 High 2.176050e-02 6.103080e-04
Te-127 U-238 Fast 1.360110e-03 8.148500e-05
Te-127 U-238 High 1.492180e-02 4.189580e-04
Te-127 Pu-239 Thermal 5.046040e-03 3.025980e-04
Te-127 Pu-239 Fast 4.991910e-03 7.982730e-04
Te-127 Pu-239 High 2.197370e-02 1.316830e-03
Te-127 Pu-241 Thermal 2.317370e-03 9.262710e-05
Te-127 Pu-241 Fast 3.308750e-03 1.058640e-03
-----------------------------------------------------------
Te-127m U-235 Thermal 2.181820e-04 3.444750e-05
Te-127m U-235 Fast 4.250290e-04 6.640990e-05
Te-127m U-235 High 3.161430e-03 4.969070e-04
Te-127m U-238 Fast 1.896880e-04 3.117860e-05
Te-127m U-238 High 2.085290e-03 3.154870e-04
Te-127m Pu-239 Thermal 7.037610e-04 1.168370e-04
Te-127m Pu-239 Fast 6.962120e-04 3.756260e-04
Te-127m Pu-239 High 3.478650e-03 7.706530e-04
Te-127m Pu-241 Thermal 3.231930e-04 5.082170e-05
Te-127m Pu-241 Fast 4.614570e-04 2.491200e-04
-----------------------------------------------------------
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