62-Sm-149
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)
148.917192062 ± 0.000001839 (amu) [mass excess = -77135.097 ± 1.714 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-694.616 ± 3.792 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sm-149.
Figures of cross sections, Sm-149: 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-148 (Z= 62, A=148), MT=102 (n,γ)
Sm-149 (Z= 62, A=149), MT= 2 (Elastic scattering)
Sm-149 (Z= 62, A=149), MT= 4 (Inelastic scattering)
Sm-150 (Z= 62, A=150), MT= 16 (n,2n)
Sm-151 (Z= 62, A=151), MT= 17 (n,3n)
Eu-151 (Z= 63, A=151), MT= 32 (n,nd)
Eu-151 (Z= 63, A=151), MT= 41 (n,2np)
Eu-151 (Z= 63, A=151), MT=105 (n,t)
Eu-152 (Z= 63, A=152), MT= 33 (n,nt)
Gd-152 (Z= 64, A=152), MT=107 (n,α)
Gd-153 (Z= 64, A=153), MT= 22 (n,nα)
Gd-154 (Z= 64, A=154), MT= 24 (n,2nα)
Dy-156 (Z= 66, A=156), 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-149 U-235 Thermal 1.707280e-12 1.092660e-12
Sm-149 U-235 Fast 5.708210e-13 3.653260e-13
Sm-149 U-235 High 2.663650e-08 1.704740e-08
Sm-149 U-238 Fast 1.570590e-14 1.005180e-14
Sm-149 U-238 High 2.292500e-11 1.467200e-11
Sm-149 Pu-239 Thermal 8.188710e-10 5.240780e-10
Sm-149 Pu-239 Fast 9.428470e-10 6.034220e-10
Sm-149 Pu-239 High 9.976470e-07 6.384940e-07
Sm-149 Pu-241 Thermal 7.181150e-13 4.595940e-13
Sm-149 Pu-241 Fast 4.256800e-12 2.724350e-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)
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Sm-149 U-235 Thermal 1.079850e-02 1.096110e-04
Sm-149 U-235 Fast 1.034620e-02 7.630660e-05
Sm-149 U-235 High 8.143510e-03 1.301150e-03
Sm-149 U-238 Fast 1.623790e-02 1.632240e-04
Sm-149 U-238 High 1.458870e-02 8.749210e-04
Sm-149 Pu-239 Thermal 1.216310e-02 8.519260e-05
Sm-149 Pu-239 Fast 1.240860e-02 6.210280e-05
Sm-149 Pu-239 High 1.055870e-02 1.160750e-03
Sm-149 Pu-241 Thermal 1.473800e-02 2.063880e-04
Sm-149 Pu-241 Fast 1.457110e-02 2.047200e-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