63-Eu-156
Spin
Level energy(keV) Spin & Parity
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ground state 0+
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)
155.924760494 ± 0.000005927 (amu) [mass excess = -70085.148 ± 5.521 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2449.134 ± 5.283 (keV)
Strong Gamma-rays from Decay of Eu-156 (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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88.97 8.44 B-
811.77 9.7 B-
1230.71 7.98 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- 15.19 D 8
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Eu-156.
Figures of cross sections, Eu-156: 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
Eu-155 (Z= 63, A=155), MT=102 (n,γ)
Eu-156 (Z= 63, A=156), MT= 2 (Elastic scattering)
Eu-156 (Z= 63, A=156), MT= 4 (Inelastic scattering)
Eu-157 (Z= 63, A=157), MT= 16 (n,2n)
Gd-156 (Z= 64, A=156), MT=103 (n,p)
Gd-157 (Z= 64, A=157), MT= 28 (n,np)
Gd-157 (Z= 64, A=157), MT=104 (n,d)
Gd-158 (Z= 64, A=158), MT= 32 (n,nd)
Gd-158 (Z= 64, A=158), MT=105 (n,t)
Tb-159 (Z= 65, A=159), MT=107 (n,α)
Tb-160 (Z= 65, A=160), 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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Eu-156 U-235 Thermal 1.617430e-07 1.035150e-07
Eu-156 U-235 Fast 8.262940e-08 5.288280e-08
Eu-156 U-235 High 3.278490e-05 2.098230e-05
Eu-156 U-238 Fast 2.380890e-08 1.523770e-08
Eu-156 U-238 High 9.700560e-07 6.208360e-07
Eu-156 Pu-239 Thermal 1.177820e-05 7.538020e-06
Eu-156 Pu-239 Fast 2.008670e-05 1.285550e-05
Eu-156 Pu-239 High 3.856900e-04 2.468420e-04
Eu-156 Pu-241 Thermal 5.300860e-07 3.392550e-07
Eu-156 Pu-241 Fast 2.508110e-06 1.605190e-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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Eu-156 U-235 Thermal 1.483030e-04 5.945500e-06
Eu-156 U-235 Fast 2.021700e-04 4.073310e-06
Eu-156 U-235 High 5.793280e-04 1.621980e-05
Eu-156 U-238 Fast 7.606120e-04 1.520920e-05
Eu-156 U-238 High 1.144930e-03 3.204760e-05
Eu-156 Pu-239 Thermal 1.239950e-03 4.960530e-05
Eu-156 Pu-239 Fast 1.547280e-03 9.285050e-05
Eu-156 Pu-239 High 2.123580e-03 1.273390e-04
Eu-156 Pu-241 Thermal 1.721520e-03 4.819580e-05
Eu-156 Pu-241 Fast 2.440680e-03 7.816050e-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