60-Nd-145
Spin
Level energy(keV) Spin & Parity
----------------------------------------
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)
144.912579322 ± 0.000001953 (amu) [mass excess = -81431.837 ± 1.819 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-164.515 ± 2.537 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-145.
Figures of cross sections, Nd-145: 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-144 (Z= 60, A=144), MT=102 (n,γ)
Nd-145 (Z= 60, A=145), MT= 2 (Elastic scattering)
Nd-145 (Z= 60, A=145), MT= 4 (Inelastic scattering)
Nd-146 (Z= 60, A=146), MT= 16 (n,2n)
Nd-147 (Z= 60, A=147), MT= 17 (n,3n)
Pm-147 (Z= 61, A=147), MT= 32 (n,nd)
Pm-147 (Z= 61, A=147), MT= 41 (n,2np)
Pm-147 (Z= 61, A=147), MT=105 (n,t)
Pm-148 (Z= 61, A=148), MT= 33 (n,nt)
Pm-148 (Z= 61, A=148), MT= 33 (n,nt)
Sm-147 (Z= 62, A=147), MT=106 (n,3He)
Sm-148 (Z= 62, A=148), MT=107 (n,α)
Sm-149 (Z= 62, A=149), MT= 22 (n,nα)
Sm-150 (Z= 62, A=150), MT= 24 (n,2nα)
Gd-152 (Z= 64, A=152), MT=108 (n,2α)
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-145 U-235 Thermal 5.541180e-10 3.546350e-10
Nd-145 U-235 Fast 1.826230e-10 1.168790e-10
Nd-145 U-235 High 8.351440e-07 5.344930e-07
Nd-145 U-238 Fast 5.341990e-12 3.418870e-12
Nd-145 U-238 High 1.942120e-09 1.242960e-09
Nd-145 Pu-239 Thermal 5.929070e-08 3.794600e-08
Nd-145 Pu-239 Fast 7.538780e-08 4.824820e-08
Nd-145 Pu-239 High 1.217790e-05 7.793850e-06
Nd-145 Pu-241 Thermal 2.110340e-10 1.350620e-10
Nd-145 Pu-241 Fast 7.094660e-10 4.540590e-10
-----------------------------------------------------------
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-145 U-235 Thermal 3.927250e-02 1.506780e-04
Nd-145 U-235 Fast 3.767680e-02 2.051160e-04
Nd-145 U-235 High 2.712940e-02 1.625870e-03
Nd-145 U-238 Fast 3.809330e-02 2.666500e-04
Nd-145 U-238 High 3.006550e-02 1.201840e-03
Nd-145 Pu-239 Thermal 2.985780e-02 1.046360e-04
Nd-145 Pu-239 Fast 3.003660e-02 1.502800e-04
Nd-145 Pu-239 High 2.159450e-02 1.726510e-03
Nd-145 Pu-241 Thermal 3.263160e-02 3.263000e-04
Nd-145 Pu-241 Fast 3.323970e-02 3.337810e-04
-----------------------------------------------------------
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