68-Er-167
Spin
Level energy(keV) Spin & Parity
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ground state 7/2+
2.07801E+02 1/2-
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)
166.932054617 ± 0.000002180 (amu) [mass excess = -63290.716 ± 2.031 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-746.662 ± 1.524 (keV)
Strong Gamma-rays from Decay of Er-167 (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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207.80 42.4 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 2.269 S 6
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Er-167.
Figures of cross sections, Er-167: 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
Er-166 (Z= 68, A=166), MT=102 (n,γ)
Er-167 (Z= 68, A=167), MT= 2 (Elastic scattering)
Er-167 (Z= 68, A=167), MT= 4 (Inelastic scattering)
Er-168 (Z= 68, A=168), MT= 16 (n,2n)
Tm-169 (Z= 69, A=169), MT= 32 (n,nd)
Tm-169 (Z= 69, A=169), MT= 41 (n,2np)
Tm-169 (Z= 69, A=169), MT=105 (n,t)
Yb-170 (Z= 70, A=170), MT=107 (n,α)
Yb-171 (Z= 70, A=171), 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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Er-167 U-235 Thermal 9.521820e-15 6.093970e-15
Er-167 U-235 Fast 3.991210e-15 3.192970e-15
Er-167 U-235 High 3.676730e-09 2.353110e-09
Er-167 U-238 Fast 1.326860e-14 1.061490e-14
Er-167 U-238 High 6.566910e-12 4.202830e-12
Er-167 Pu-239 Thermal 1.046310e-11 6.696350e-12
Er-167 Pu-239 Fast 4.458670e-10 2.853550e-10
Er-167 Pu-239 High 5.303300e-08 3.394110e-08
Er-167 Pu-241 Thermal 1.612590e-16 1.290070e-16
Er-167 Pu-241 Fast 7.614750e-12 4.873440e-12
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Er-167m U-235 Thermal 2.040240e-15 1.632190e-15
Er-167m U-235 Fast 5.339710e-16 4.271770e-16
Er-167m U-235 High 3.067260e-10 1.963050e-10
Er-167m U-238 Fast 1.775160e-15 1.420130e-15
Er-167m U-238 High 5.478360e-13 3.506150e-13
Er-167m Pu-239 Thermal 1.605060e-12 1.027240e-12
Er-167m Pu-239 Fast 5.965110e-11 3.817670e-11
Er-167m Pu-239 High 4.424210e-09 2.831490e-09
Er-167m Pu-241 Thermal 2.473760e-17 1.979000e-17
Er-167m Pu-241 Fast 1.018750e-12 6.520020e-13
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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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Er-167 U-235 Thermal 2.467630e-09 7.903470e-10
Er-167 U-235 Fast 3.835130e-09 8.856160e-10
Er-167 U-235 High 1.855540e-06 2.035560e-07
Er-167 U-238 Fast 4.353320e-07 6.960120e-08
Er-167 U-238 High 3.698690e-06 5.904670e-07
Er-167 Pu-239 Thermal 1.520870e-07 4.863950e-08
Er-167 Pu-239 Fast 2.668230e-06 8.543870e-07
Er-167 Pu-239 High 2.742340e-06 4.383440e-07
Er-167 Pu-241 Thermal 1.035990e-09 3.328240e-10
Er-167 Pu-241 Fast 3.104110e-06 9.952170e-07
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Er-167m U-235 Thermal 2.961160e-10 1.215180e-10
Er-167m U-235 Fast 4.602160e-10 1.888730e-10
Er-167m U-235 High 2.225010e-07 9.130650e-08
Er-167m U-238 Fast 5.223980e-08 1.328460e-08
Er-167m U-238 High 4.438420e-07 1.821370e-07
Er-167m Pu-239 Thermal 1.825070e-08 7.489470e-09
Er-167m Pu-239 Fast 3.201870e-07 1.313960e-07
Er-167m Pu-239 High 3.270890e-07 1.342350e-07
Er-167m Pu-241 Thermal 1.243190e-10 5.102050e-11
Er-167m Pu-241 Fast 3.724930e-07 1.528640e-07
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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