60-Nd-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)
149.920902249 ± 0.000001821 (amu) [mass excess = -73679.080 ± 1.696 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-82.616 ± 20.001 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-150.
Figures of cross sections, Nd-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
Nd-150 (Z= 60, A=150), MT= 2 (Elastic scattering)
Nd-150 (Z= 60, A=150), MT= 4 (Inelastic scattering)
Pm-151 (Z= 61, A=151), MT= 28 (n,np)
Pm-151 (Z= 61, A=151), MT=104 (n,d)
Sm-152 (Z= 62, A=152), MT=106 (n,3He)
Sm-153 (Z= 62, A=153), MT=107 (n,α)
Sm-154 (Z= 62, A=154), 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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Nd-150 U-235 Thermal 3.267300e-04 2.091070e-04
Nd-150 U-235 Fast 2.015740e-04 1.290070e-04
Nd-150 U-235 High 1.200890e-03 7.685730e-04
Nd-150 U-238 Fast 4.262590e-05 2.728060e-05
Nd-150 U-238 High 2.707650e-04 1.732900e-04
Nd-150 Pu-239 Thermal 1.736790e-03 1.111540e-03
Nd-150 Pu-239 Fast 1.912870e-03 1.224230e-03
Nd-150 Pu-239 High 4.073220e-03 2.606860e-03
Nd-150 Pu-241 Thermal 2.550310e-04 1.632190e-04
Nd-150 Pu-241 Fast 4.510510e-04 2.886730e-04
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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)
-----------------------------------------------------------
Nd-150 U-235 Thermal 6.523220e-03 3.395100e-05
Nd-150 U-235 Fast 6.845320e-03 3.657630e-05
Nd-150 U-235 High 5.116600e-03 5.620210e-04
Nd-150 U-238 Fast 1.276260e-02 1.303820e-04
Nd-150 U-238 High 1.082940e-02 1.729540e-03
Nd-150 Pu-239 Thermal 9.661870e-03 3.383760e-05
Nd-150 Pu-239 Fast 9.945130e-03 4.974480e-05
Nd-150 Pu-239 High 9.392610e-03 1.501840e-03
Nd-150 Pu-241 Thermal 1.210000e-02 1.210940e-04
Nd-150 Pu-241 Fast 1.229620e-02 1.231980e-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