62-Sm-154
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)
153.922216861 ± 0.000001964 (amu) [mass excess = -72454.527 ± 1.830 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-717.345 ± 1.092 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sm-154.
Figures of cross sections, Sm-154: 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-153 (Z= 62, A=153), MT=102 (n,γ)
Sm-154 (Z= 62, A=154), MT= 2 (Elastic scattering)
Sm-154 (Z= 62, A=154), MT= 4 (Inelastic scattering)
Eu-154 (Z= 63, A=154), MT=103 (n,p)
Eu-155 (Z= 63, A=155), MT= 28 (n,np)
Eu-155 (Z= 63, A=155), MT=104 (n,d)
Eu-156 (Z= 63, A=156), MT= 32 (n,nd)
Eu-156 (Z= 63, A=156), MT= 41 (n,2np)
Eu-156 (Z= 63, A=156), MT=105 (n,t)
Eu-157 (Z= 63, A=157), MT= 33 (n,nt)
Gd-156 (Z= 64, A=156), MT=106 (n,3He)
Gd-157 (Z= 64, A=157), MT=107 (n,α)
Gd-158 (Z= 64, A=158), 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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Sm-154 U-235 Thermal 4.722480e-06 3.022390e-06
Sm-154 U-235 Fast 2.085690e-06 1.334850e-06
Sm-154 U-235 High 1.322310e-04 8.462800e-05
Sm-154 U-238 Fast 4.391640e-07 2.810650e-07
Sm-154 U-238 High 9.600450e-06 6.144290e-06
Sm-154 Pu-239 Thermal 9.374520e-05 5.999700e-05
Sm-154 Pu-239 Fast 1.298090e-04 8.307770e-05
Sm-154 Pu-239 High 8.255250e-04 5.283370e-04
Sm-154 Pu-241 Thermal 6.871100e-06 4.397510e-06
Sm-154 Pu-241 Fast 1.840620e-05 1.177990e-05
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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-154 U-235 Thermal 7.432760e-04 7.518560e-06
Sm-154 U-235 Fast 7.218670e-04 7.350710e-06
Sm-154 U-235 High 1.268520e-03 2.913230e-04
Sm-154 U-238 Fast 2.166660e-03 2.196680e-05
Sm-154 U-238 High 2.525590e-03 4.034190e-04
Sm-154 Pu-239 Thermal 2.597320e-03 3.636690e-05
Sm-154 Pu-239 Fast 2.671720e-03 3.740870e-05
Sm-154 Pu-239 High 3.215740e-03 5.141850e-04
Sm-154 Pu-241 Thermal 3.793400e-03 7.585630e-05
Sm-154 Pu-241 Fast 3.811730e-03 7.628260e-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