62-Sm-152
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)
151.919739721 ± 0.000001759 (amu) [mass excess = -74761.968 ± 1.639 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1874.597 ± 0.675 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sm-152.
Figures of cross sections, Sm-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
Sm-151 (Z= 62, A=151), MT=102 (n,γ)
Sm-152 (Z= 62, A=152), MT= 2 (Elastic scattering)
Sm-152 (Z= 62, A=152), MT= 4 (Inelastic scattering)
Sm-153 (Z= 62, A=153), MT= 16 (n,2n)
Sm-154 (Z= 62, A=154), MT= 17 (n,3n)
Eu-152 (Z= 63, A=152), MT=103 (n,p)
Eu-153 (Z= 63, A=153), MT= 28 (n,np)
Eu-153 (Z= 63, A=153), MT=104 (n,d)
Eu-154 (Z= 63, A=154), MT= 32 (n,nd)
Eu-154 (Z= 63, A=154), MT= 41 (n,2np)
Eu-154 (Z= 63, A=154), MT=105 (n,t)
Eu-155 (Z= 63, A=155), MT= 33 (n,nt)
Gd-154 (Z= 64, A=154), MT=106 (n,3He)
Gd-155 (Z= 64, A=155), MT=107 (n,α)
Gd-156 (Z= 64, A=156), MT= 22 (n,nα)
Gd-157 (Z= 64, A=157), 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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Sm-152 U-235 Thermal 9.634660e-08 6.166180e-08
Sm-152 U-235 Fast 4.081570e-08 2.612210e-08
Sm-152 U-235 High 1.425960e-05 9.126110e-06
Sm-152 U-238 Fast 2.500940e-09 1.600600e-09
Sm-152 U-238 High 2.342550e-07 1.499240e-07
Sm-152 Pu-239 Thermal 4.299330e-06 2.751570e-06
Sm-152 Pu-239 Fast 6.089010e-06 3.896970e-06
Sm-152 Pu-239 High 1.715810e-04 1.098120e-04
Sm-152 Pu-241 Thermal 6.110990e-08 3.911030e-08
Sm-152 Pu-241 Fast 2.188350e-07 1.400550e-07
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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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Sm-152 U-235 Thermal 2.665080e-03 2.699720e-05
Sm-152 U-235 Fast 2.702990e-03 3.832320e-05
Sm-152 U-235 High 2.579850e-03 2.834280e-04
Sm-152 U-238 Fast 5.304260e-03 5.305920e-05
Sm-152 U-238 High 5.794160e-03 9.260940e-04
Sm-152 Pu-239 Thermal 5.762260e-03 5.763710e-05
Sm-152 Pu-239 Fast 6.266010e-03 8.774140e-05
Sm-152 Pu-239 High 5.401060e-03 8.638220e-04
Sm-152 Pu-241 Thermal 7.177480e-03 1.004750e-04
Sm-152 Pu-241 Fast 7.313570e-03 1.026150e-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