60-Nd-142
Spin
Level energy(keV) Spin & Parity
----------------------------------------
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)
141.907728996 ± 0.000001953 (amu) [mass excess = -85949.886 ± 1.820 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-4807.827 ± 23.653 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-142.
Figures of cross sections, Nd-142: 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= 2 (Elastic scattering)
Nd-142 (Z= 60, A=142), MT= 4 (Inelastic scattering)
Nd-143 (Z= 60, A=143), MT= 16 (n,2n)
Nd-144 (Z= 60, A=144), MT= 17 (n,3n)
Sm-144 (Z= 62, A=144), MT= 44 (n,n2p)
Sm-144 (Z= 62, A=144), MT=106 (n,3He)
Sm-144 (Z= 62, A=144), MT=115 (n,pd)
Sm-147 (Z= 62, A=147), MT= 24 (n,2nα)
Sm-148 (Z= 62, A=148), MT= 25 (n,3nα)
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)
-----------------------------------------------------------
Nd-142 U-235 High 6.999600e-11 4.479740e-11
Nd-142 Pu-239 Thermal 3.459460e-13 2.214050e-13
Nd-142 Pu-239 Fast 4.019350e-13 2.572380e-13
Nd-142 Pu-239 High 5.443530e-09 3.483860e-09
-----------------------------------------------------------
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-142 U-235 Thermal 4.621910e-11 7.763580e-14
Nd-142 U-235 Fast 1.566510e-11 3.475520e-14
Nd-142 U-235 High 3.044390e-07 1.945390e-07
Nd-142 U-238 Fast 7.461580e-13 1.530350e-16
Nd-142 U-238 High 4.594270e-10 4.248820e-13
Nd-142 Pu-239 Thermal 1.089690e-08 6.973980e-09
Nd-142 Pu-239 Fast 1.159670e-08 7.421870e-09
Nd-142 Pu-239 High 5.147960e-06 3.289610e-06
Nd-142 Pu-241 Thermal 2.740010e-11 5.724590e-17
Nd-142 Pu-241 Fast 5.664830e-11 5.167050e-14
-----------------------------------------------------------
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