60-Nd-146
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)
145.913122628 ± 0.000001953 (amu) [mass excess = -80925.751 ± 1.819 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1471.545 ± 4.121 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-146.
Figures of cross sections, Nd-146: 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-145 (Z= 60, A=145), MT=102 (n,γ)
Nd-146 (Z= 60, A=146), MT= 2 (Elastic scattering)
Nd-146 (Z= 60, A=146), MT= 4 (Inelastic scattering)
Nd-147 (Z= 60, A=147), MT= 16 (n,2n)
Nd-148 (Z= 60, A=148), MT= 17 (n,3n)
Pm-147 (Z= 61, A=147), MT= 28 (n,np)
Pm-147 (Z= 61, A=147), MT=104 (n,d)
Pm-148 (Z= 61, A=148), MT= 32 (n,nd)
Pm-148 (Z= 61, A=148), MT= 32 (n,nd)
Pm-148 (Z= 61, A=148), MT= 41 (n,2np)
Pm-148 (Z= 61, A=148), MT= 41 (n,2np)
Pm-148 (Z= 61, A=148), MT=105 (n,t)
Pm-148 (Z= 61, A=148), MT=105 (n,t)
Pm-149 (Z= 61, A=149), MT= 33 (n,nt)
Sm-148 (Z= 62, A=148), MT=106 (n,3He)
Sm-149 (Z= 62, A=149), MT=107 (n,α)
Sm-150 (Z= 62, A=150), MT= 22 (n,nα)
Sm-151 (Z= 62, A=151), 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-146 U-235 Thermal 3.184920e-08 2.038360e-08
Nd-146 U-235 Fast 1.217490e-08 7.791910e-09
Nd-146 U-235 High 9.072430e-06 5.806360e-06
Nd-146 U-238 Fast 3.901460e-10 2.496930e-10
Nd-146 U-238 High 4.444840e-08 2.844700e-08
Nd-146 Pu-239 Thermal 8.108720e-07 5.189590e-07
Nd-146 Pu-239 Fast 1.669730e-06 1.068630e-06
Nd-146 Pu-239 High 7.676980e-05 4.913270e-05
Nd-146 Pu-241 Thermal 9.431520e-09 6.036180e-09
Nd-146 Pu-241 Fast 3.217580e-08 2.059250e-08
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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-146 U-235 Thermal 2.993600e-02 1.099750e-04
Nd-146 U-235 Fast 2.916840e-02 1.528570e-04
Nd-146 U-235 High 2.202230e-02 2.418860e-03
Nd-146 U-238 Fast 3.453750e-02 2.544360e-04
Nd-146 U-238 High 2.444490e-02 1.464110e-03
Nd-146 Pu-239 Thermal 2.457990e-02 8.604410e-05
Nd-146 Pu-239 Fast 2.459870e-02 1.230080e-04
Nd-146 Pu-239 High 1.745200e-02 1.918390e-03
Nd-146 Pu-241 Thermal 2.769050e-02 1.953920e-04
Nd-146 Pu-241 Fast 2.805360e-02 2.806130e-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