60-Nd-147
Spin
Level energy(keV) Spin & Parity
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ground state 5/2-
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)
146.916106136 ± 0.000001953 (amu) [mass excess = -78146.631 ± 1.820 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
895.303 ± 0.915 (keV)
Strong Gamma-rays from Decay of Nd-147 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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91.11 28.08 B-
319.41 2.13 B-
531.02 13.37 B-
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 10.98 D 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-147.
Figures of cross sections, Nd-147: 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-146 (Z= 60, A=146), MT=102 (n,γ)
Nd-147 (Z= 60, A=147), MT= 2 (Elastic scattering)
Nd-147 (Z= 60, A=147), MT= 4 (Inelastic scattering)
Nd-148 (Z= 60, A=148), MT= 16 (n,2n)
Pm-147 (Z= 61, A=147), MT=103 (n,p)
Pm-148 (Z= 61, A=148), MT= 28 (n,np)
Pm-148 (Z= 61, A=148), MT= 28 (n,np)
Pm-148 (Z= 61, A=148), MT=104 (n,d)
Pm-148 (Z= 61, A=148), MT=104 (n,d)
Pm-149 (Z= 61, A=149), MT= 32 (n,nd)
Pm-149 (Z= 61, A=149), MT= 41 (n,2np)
Pm-149 (Z= 61, A=149), MT=105 (n,t)
Sm-149 (Z= 62, A=149), MT=106 (n,3He)
Sm-150 (Z= 62, A=150), MT=107 (n,α)
Sm-151 (Z= 62, A=151), MT= 22 (n,nα)
Sm-152 (Z= 62, A=152), 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-147 U-235 Thermal 6.709320e-07 4.293970e-07
Nd-147 U-235 Fast 2.804220e-07 1.794690e-07
Nd-147 U-235 High 5.937140e-05 3.799770e-05
Nd-147 U-238 Fast 1.430530e-08 9.155410e-09
Nd-147 U-238 High 7.948650e-07 5.087140e-07
Nd-147 Pu-239 Thermal 1.586750e-05 1.015520e-05
Nd-147 Pu-239 Fast 1.717720e-05 1.099340e-05
Nd-147 Pu-239 High 3.982580e-04 2.548850e-04
Nd-147 Pu-241 Thermal 2.330380e-07 1.491440e-07
Nd-147 Pu-241 Fast 7.134640e-07 4.566170e-07
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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-147 U-235 Thermal 2.242530e-02 3.173390e-04
Nd-147 U-235 Fast 2.133580e-02 2.203280e-04
Nd-147 U-235 High 1.625540e-02 4.551050e-04
Nd-147 U-238 Fast 2.588670e-02 3.652620e-04
Nd-147 U-238 High 2.089580e-02 4.185230e-04
Nd-147 Pu-239 Thermal 2.002590e-02 5.608400e-04
Nd-147 Pu-239 Fast 1.990330e-02 2.786980e-04
Nd-147 Pu-239 High 1.710300e-02 1.025590e-03
Nd-147 Pu-241 Thermal 2.284170e-02 6.398330e-04
Nd-147 Pu-241 Fast 2.221590e-02 1.779550e-03
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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