62-Sm-150
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)
149.917282919 ± 0.000001809 (amu) [mass excess = -77050.464 ± 1.685 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2258.642 ± 6.190 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sm-150.
Figures of cross sections, Sm-150: 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-149 (Z= 62, A=149), MT=102 (n,γ)
Sm-150 (Z= 62, A=150), MT= 2 (Elastic scattering)
Sm-150 (Z= 62, A=150), MT= 4 (Inelastic scattering)
Sm-151 (Z= 62, A=151), MT= 16 (n,2n)
Sm-152 (Z= 62, A=152), MT= 17 (n,3n)
Eu-151 (Z= 63, A=151), MT= 28 (n,np)
Eu-151 (Z= 63, A=151), MT=104 (n,d)
Eu-152 (Z= 63, A=152), MT= 32 (n,nd)
Eu-152 (Z= 63, A=152), MT= 41 (n,2np)
Eu-152 (Z= 63, A=152), MT=105 (n,t)
Eu-153 (Z= 63, A=153), MT= 33 (n,nt)
Gd-152 (Z= 64, A=152), MT=106 (n,3He)
Gd-153 (Z= 64, A=153), MT=107 (n,α)
Gd-154 (Z= 64, A=154), MT= 22 (n,nα)
Gd-155 (Z= 64, A=155), 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-150 U-235 Thermal 1.218060e-10 7.795590e-11
Sm-150 U-235 Fast 4.560580e-11 2.918770e-11
Sm-150 U-235 High 3.064200e-07 1.961090e-07
Sm-150 U-238 Fast 1.710640e-12 1.094810e-12
Sm-150 U-238 High 7.628300e-10 4.882120e-10
Sm-150 Pu-239 Thermal 2.539600e-08 1.625340e-08
Sm-150 Pu-239 Fast 3.239470e-08 2.073260e-08
Sm-150 Pu-239 High 9.586220e-06 6.135180e-06
Sm-150 Pu-241 Thermal 6.100990e-11 3.904630e-11
Sm-150 Pu-241 Fast 2.797900e-10 1.790650e-10
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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)
-----------------------------------------------------------
Sm-150 U-235 Thermal 2.996450e-07 1.917720e-07
Sm-150 U-235 Fast 2.505290e-07 1.603390e-07
Sm-150 U-235 High 9.348950e-06 5.970550e-06
Sm-150 U-238 Fast 3.291400e-08 2.105610e-08
Sm-150 U-238 High 2.530370e-07 1.612840e-07
Sm-150 Pu-239 Thermal 1.152360e-05 7.372710e-06
Sm-150 Pu-239 Fast 2.227880e-05 1.425840e-05
Sm-150 Pu-239 High 5.515360e-04 3.527420e-04
Sm-150 Pu-241 Thermal 5.081430e-07 3.251200e-07
Sm-150 Pu-241 Fast 1.119440e-06 7.164400e-07
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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