60-Nd-143
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)
142.909819989 ± 0.000001953 (amu) [mass excess = -84002.139 ± 1.819 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1041.664 ± 2.687 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-143.
Figures of cross sections, Nd-143: 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-142 (Z= 60, A=142), MT=102 (n,γ)
Nd-143 (Z= 60, A=143), MT= 2 (Elastic scattering)
Nd-143 (Z= 60, A=143), MT= 4 (Inelastic scattering)
Nd-144 (Z= 60, A=144), MT= 16 (n,2n)
Nd-145 (Z= 60, A=145), MT= 17 (n,3n)
Sm-144 (Z= 62, A=144), MT=111 (n,2p)
Sm-147 (Z= 62, A=147), MT= 22 (n,nα)
Sm-148 (Z= 62, A=148), 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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Nd-143 U-235 Thermal 4.792370e-14 3.067110e-14
Nd-143 U-235 Fast 1.367180e-14 8.749930e-15
Nd-143 U-235 High 2.393280e-09 1.531700e-09
Nd-143 U-238 High 7.007630e-13 4.484880e-13
Nd-143 Pu-239 Thermal 2.909540e-11 1.862110e-11
Nd-143 Pu-239 Fast 3.509430e-11 2.246040e-11
Nd-143 Pu-239 High 9.726310e-08 6.224840e-08
Nd-143 Pu-241 Thermal 1.810290e-14 1.158590e-14
Nd-143 Pu-241 Fast 6.325240e-14 4.048160e-14
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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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Nd-143 U-235 Thermal 5.947850e-02 2.229590e-04
Nd-143 U-235 Fast 5.721970e-02 3.009190e-04
Nd-143 U-235 High 3.821190e-02 1.069950e-03
Nd-143 U-238 Fast 4.632000e-02 9.910390e-05
Nd-143 U-238 High 3.917170e-02 7.863460e-04
Nd-143 Pu-239 Thermal 4.412790e-02 2.207000e-04
Nd-143 Pu-239 Fast 4.341530e-02 1.520200e-04
Nd-143 Pu-239 High 2.809720e-02 1.684800e-03
Nd-143 Pu-241 Thermal 4.581110e-02 3.219680e-04
Nd-143 Pu-241 Fast 4.669970e-02 4.672950e-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