63-Eu-152
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 3-
4.55998E+01 0-
1.47810E+02 8-
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)
151.921752184 ± 0.000001843 (amu) [mass excess = -72887.371 ± 1.717 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1818.919 ± 0.689 (keV)
Strong Gamma-rays from Decay of Eu-152 (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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121.78 28.67 EC
964.08 14.65 EC
1408.01 21.07 EC
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121.78 7. EC
841.59 14.18 EC
963.39 11.67 EC
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18.21 1.26 IT
77.23 0.69 IT
89.85 69.9 IT
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344.31 2.38 B-
970.35 0.59 B-
1314.67 0.93 B-
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344.28 26.56 B-
411.12 2.24 B-
778.90 12.96 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- 9.3116 H 13
B- 13.537 Y 6
EC 9.3116 H 13
EC 13.537 Y 6
IT 96 M 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Eu-152.
Figures of cross sections, Eu-152: 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-151 (Z= 63, A=151), MT=102 (n,γ)
Eu-152 (Z= 63, A=152), MT= 2 (Elastic scattering)
Eu-152 (Z= 63, A=152), MT= 4 (Inelastic scattering)
Eu-153 (Z= 63, A=153), MT= 16 (n,2n)
Eu-154 (Z= 63, A=154), MT= 17 (n,3n)
Gd-152 (Z= 64, A=152), MT=103 (n,p)
Gd-153 (Z= 64, A=153), MT= 28 (n,np)
Gd-153 (Z= 64, A=153), MT=104 (n,d)
Gd-154 (Z= 64, A=154), MT= 32 (n,nd)
Gd-154 (Z= 64, A=154), MT=105 (n,t)
Dy-156 (Z= 66, A=156), MT=112 (n,pα)
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-152 U-235 Thermal 1.349690e-12 8.638030e-13
Eu-152 U-235 Fast 4.287390e-13 2.743930e-13
Eu-152 U-235 High 1.662120e-08 1.063760e-08
Eu-152 U-238 Fast 2.011170e-14 1.287150e-14
Eu-152 U-238 High 2.152740e-11 1.377760e-11
Eu-152 Pu-239 Thermal 6.748200e-10 4.318840e-10
Eu-152 Pu-239 Fast 1.000460e-09 6.402920e-10
Eu-152 Pu-239 High 7.127830e-07 4.561810e-07
Eu-152 Pu-241 Thermal 1.153230e-12 7.380650e-13
Eu-152 Pu-241 Fast 5.705670e-12 3.651630e-12
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Eu-152m U-235 Thermal 1.520780e-13 9.732990e-14
Eu-152m U-235 Thermal 1.213910e-12 7.769010e-13
Eu-152m U-235 Fast 4.203320e-14 2.690120e-14
Eu-152m U-235 Fast 4.623650e-13 2.959140e-13
Eu-152m U-235 High 1.038820e-09 6.648490e-10
Eu-152m U-235 High 3.180780e-08 2.035700e-08
Eu-152m U-238 Fast 1.971740e-15 1.261910e-15
Eu-152m U-238 Fast 2.168910e-14 1.388100e-14
Eu-152m U-238 High 1.345460e-12 8.610980e-13
Eu-152m U-238 High 4.119680e-11 2.636600e-11
Eu-152m Pu-239 Thermal 7.603600e-11 4.866300e-11
Eu-152m Pu-239 Thermal 6.069300e-10 3.884350e-10
Eu-152m Pu-239 Fast 9.808410e-11 6.277380e-11
Eu-152m Pu-239 Fast 1.078930e-09 6.905110e-10
Eu-152m Pu-239 High 4.454890e-08 2.851130e-08
Eu-152m Pu-239 High 1.364050e-06 8.729890e-07
Eu-152m Pu-241 Thermal 1.299410e-13 8.316220e-14
Eu-152m Pu-241 Thermal 1.037210e-12 6.638130e-13
Eu-152m Pu-241 Fast 5.593800e-13 3.580030e-13
Eu-152m Pu-241 Fast 6.153180e-12 3.938040e-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)
-----------------------------------------------------------
Eu-152 U-235 Thermal 2.563600e-12 1.382010e-12
Eu-152 U-235 Fast 8.911040e-13 4.835210e-13
Eu-152 U-235 High 4.842900e-08 2.845120e-08
Eu-152 U-238 Fast 4.180080e-14 2.269070e-14
Eu-152 U-238 High 6.272420e-11 3.684340e-11
Eu-152 Pu-239 Thermal 1.281750e-09 6.909980e-10
Eu-152 Pu-239 Fast 2.079380e-09 1.128650e-09
Eu-152 Pu-239 High 2.076830e-06 1.219680e-06
Eu-152 Pu-241 Thermal 2.190430e-12 1.180880e-12
Eu-152 Pu-241 Fast 1.185890e-11 6.436120e-12
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Eu-152m U-235 Thermal 1.520780e-13 9.733010e-14
Eu-152m U-235 Thermal 1.213910e-12 7.769010e-13
Eu-152m U-235 Fast 4.203320e-14 2.690120e-14
Eu-152m U-235 Fast 4.623650e-13 2.959140e-13
Eu-152m U-235 High 1.038820e-09 6.648470e-10
Eu-152m U-235 High 3.180780e-08 2.032690e-08
Eu-152m U-238 Fast 1.971740e-15 1.261910e-15
Eu-152m U-238 Fast 2.168910e-14 1.387590e-14
Eu-152m U-238 High 1.345460e-12 8.610980e-13
Eu-152m U-238 High 4.119680e-11 2.633740e-11
Eu-152m Pu-239 Thermal 7.603600e-11 4.866310e-11
Eu-152m Pu-239 Thermal 6.069300e-10 3.884350e-10
Eu-152m Pu-239 Fast 9.808410e-11 6.277390e-11
Eu-152m Pu-239 Fast 1.078930e-09 6.905110e-10
Eu-152m Pu-239 High 4.454890e-08 2.851130e-08
Eu-152m Pu-239 High 1.364050e-06 8.724240e-07
Eu-152m Pu-241 Thermal 1.299410e-13 8.316210e-14
Eu-152m Pu-241 Thermal 1.037210e-12 6.637050e-13
Eu-152m Pu-241 Fast 5.593800e-13 3.580030e-13
Eu-152m Pu-241 Fast 6.153180e-12 3.938040e-12
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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