64-Gd-153
Spin
Level energy(keV) Spin & Parity
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ground state 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)
152.921758027 ± 0.000001751 (amu) [mass excess = -72881.928 ± 1.632 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1568.987 ± 3.852 (keV)
Strong Gamma-rays from Decay of Gd-153 (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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69.67 2.42 EC
97.43 29. EC
103.18 21.11 EC
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41.56 9. IT
51.78 4.5 IT
93.34 0.99 IT
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41.56 9. IT
51.78 4.5 IT
76.01 18.9 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
EC 240.4 D 10
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Gd-153.
Figures of cross sections, Gd-153: 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
Gd-152 (Z= 64, A=152), MT=102 (n,γ)
Gd-153 (Z= 64, A=153), MT= 2 (Elastic scattering)
Gd-153 (Z= 64, A=153), MT= 4 (Inelastic scattering)
Gd-154 (Z= 64, A=154), MT= 16 (n,2n)
Gd-155 (Z= 64, A=155), MT= 17 (n,3n)
Dy-154 (Z= 66, A=154), MT=111 (n,2p)
Dy-156 (Z= 66, A=156), MT=107 (n,α)
Dy-158 (Z= 66, A=158), MT= 24 (n,2nα)
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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Gd-153 U-235 High 4.325930e-10 2.768600e-10
Gd-153 U-238 High 7.558230e-14 4.837270e-14
Gd-153 Pu-239 Thermal 2.169650e-12 1.388580e-12
Gd-153 Pu-239 Fast 5.019190e-12 3.212280e-12
Gd-153 Pu-239 High 4.933200e-08 3.157250e-08
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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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Gd-153 U-235 High 4.325930e-10 2.764500e-10
Gd-153 U-238 High 7.558230e-14 4.832030e-14
Gd-153 Pu-239 Thermal 2.169650e-12 1.388580e-12
Gd-153 Pu-239 Fast 5.019190e-12 3.212280e-12
Gd-153 Pu-239 High 4.933200e-08 3.155200e-08
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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