58-Ce-143
Spin
Level energy(keV) Spin & Parity
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ground state 3/2-
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)
142.912392120 ± 0.000002909 (amu) [mass excess = -81606.215 ± 2.711 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1461.816 ± 1.829 (keV)
Strong Gamma-rays from Decay of Ce-143 (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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57.36 11.73 B-
293.27 42.8 B-
664.57 5.69 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- 33.039 H 6
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ce-143.
Figures of cross sections, Ce-143: 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
Ce-142 (Z= 58, A=142), MT=102 (n,γ)
Ce-143 (Z= 58, A=143), MT= 2 (Elastic scattering)
Ce-143 (Z= 58, A=143), MT= 4 (Inelastic scattering)
Ce-144 (Z= 58, A=144), MT= 16 (n,2n)
Pr-143 (Z= 59, A=143), MT=103 (n,p)
Nd-145 (Z= 60, A=145), MT=106 (n,3He)
Nd-146 (Z= 60, A=146), MT=107 (n,α)
Nd-147 (Z= 60, A=147), MT= 22 (n,nα)
Nd-148 (Z= 60, A=148), 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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Ce-143 U-235 Thermal 3.128720e-04 3.441590e-05
Ce-143 U-235 Fast 1.390130e-05 8.896830e-06
Ce-143 U-235 High 6.315960e-04 4.042210e-04
Ce-143 U-238 Fast 9.013360e-07 5.768550e-07
Ce-143 U-238 High 1.817980e-05 1.163500e-05
Ce-143 Pu-239 Thermal 2.665380e-04 1.705840e-04
Ce-143 Pu-239 Fast 2.885330e-04 1.846610e-04
Ce-143 Pu-239 High 1.967330e-03 1.259090e-03
Ce-143 Pu-241 Thermal 1.120180e-05 7.169150e-06
Ce-143 Pu-241 Fast 1.906570e-05 1.220200e-05
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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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Ce-143 U-235 Thermal 5.947850e-02 8.375510e-04
Ce-143 U-235 Fast 5.721970e-02 8.076020e-04
Ce-143 U-235 High 3.820790e-02 1.069840e-03
Ce-143 U-238 Fast 4.632000e-02 6.546370e-04
Ce-143 U-238 High 3.917160e-02 7.863450e-04
Ce-143 Pu-239 Thermal 4.412760e-02 6.178580e-04
Ce-143 Pu-239 Fast 4.341490e-02 2.171300e-04
Ce-143 Pu-239 High 2.805850e-02 1.682480e-03
Ce-143 Pu-241 Thermal 4.581110e-02 9.161300e-04
Ce-143 Pu-241 Fast 4.669970e-02 1.868530e-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