60-Nd-148
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)
147.916899294 ± 0.000002594 (amu) [mass excess = -77407.809 ± 2.417 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-542.735 ± 5.915 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nd-148.
Figures of cross sections, Nd-148: 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-147 (Z= 60, A=147), MT=102 (n,γ)
Nd-148 (Z= 60, A=148), MT= 2 (Elastic scattering)
Nd-148 (Z= 60, A=148), MT= 4 (Inelastic scattering)
Nd-150 (Z= 60, A=150), MT= 17 (n,3n)
Pm-148 (Z= 61, A=148), MT=103 (n,p)
Pm-148 (Z= 61, A=148), MT=103 (n,p)
Pm-149 (Z= 61, A=149), MT= 28 (n,np)
Pm-149 (Z= 61, A=149), MT=104 (n,d)
Pm-151 (Z= 61, A=151), MT= 33 (n,nt)
Sm-150 (Z= 62, A=150), MT=106 (n,3He)
Sm-151 (Z= 62, A=151), MT=107 (n,α)
Sm-152 (Z= 62, A=152), MT= 22 (n,nα)
Sm-153 (Z= 62, A=153), 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-148 U-235 Thermal 9.914210e-06 6.345100e-06
Nd-148 U-235 Fast 5.169330e-06 3.308370e-06
Nd-148 U-235 High 2.588350e-04 1.656540e-04
Nd-148 U-238 Fast 3.591340e-07 2.298450e-07
Nd-148 U-238 High 8.969770e-06 5.740650e-06
Nd-148 Pu-239 Thermal 1.372780e-04 8.785810e-05
Nd-148 Pu-239 Fast 1.347090e-04 8.621330e-05
Nd-148 Pu-239 High 1.114670e-03 7.133910e-04
Nd-148 Pu-241 Thermal 4.270690e-06 2.733240e-06
Nd-148 Pu-241 Fast 1.088180e-05 6.964360e-06
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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-148 U-235 Thermal 1.670620e-02 6.545330e-05
Nd-148 U-235 Fast 1.679510e-02 9.285080e-05
Nd-148 U-235 High 1.199450e-02 1.317730e-03
Nd-148 U-238 Fast 2.112040e-02 1.479470e-04
Nd-148 U-238 High 1.731600e-02 2.768840e-03
Nd-148 Pu-239 Thermal 1.641740e-02 8.217940e-05
Nd-148 Pu-239 Fast 1.660980e-02 5.830660e-05
Nd-148 Pu-239 High 1.293700e-02 1.422240e-03
Nd-148 Pu-241 Thermal 1.931670e-02 1.353170e-04
Nd-148 Pu-241 Fast 1.954150e-02 1.966700e-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