62-Sm-147
Spin
Level energy(keV) Spin & Parity
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ground state 7/2-
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)
146.914904435 ± 0.000001919 (amu) [mass excess = -79266.008 ± 1.788 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1721.609 ± 2.302 (keV)
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
A 1.06E+11 Y 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sm-147.
Figures of cross sections, Sm-147: 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-147 (Z= 62, A=147), MT= 2 (Elastic scattering)
Sm-147 (Z= 62, A=147), MT= 4 (Inelastic scattering)
Sm-148 (Z= 62, A=148), MT= 16 (n,2n)
Sm-149 (Z= 62, A=149), MT= 17 (n,3n)
Gd-152 (Z= 64, A=152), MT= 24 (n,2nα)
Dy-154 (Z= 66, A=154), MT=108 (n,2α)
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-147 U-235 High 4.315910e-11 2.762190e-11
Sm-147 Pu-239 Thermal 1.829710e-13 1.171020e-13
Sm-147 Pu-239 Fast 2.259630e-13 1.446160e-13
Sm-147 Pu-239 High 4.953210e-09 3.170060e-09
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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-147 U-235 Thermal 2.242530e-02 4.204360e-05
Sm-147 U-235 Fast 2.133580e-02 5.288610e-05
Sm-147 U-235 High 1.625550e-02 4.551140e-04
Sm-147 U-238 Fast 2.588670e-02 4.073600e-05
Sm-147 U-238 High 2.089580e-02 1.567040e-05
Sm-147 Pu-239 Thermal 2.002590e-02 2.003300e-04
Sm-147 Pu-239 Fast 1.990330e-02 1.393680e-04
Sm-147 Pu-239 High 1.710710e-02 1.025840e-03
Sm-147 Pu-241 Thermal 2.284170e-02 7.832420e-06
Sm-147 Pu-241 Fast 2.221590e-02 2.612360e-05
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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