58-Ce-144
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)
143.913652939 ± 0.000003354 (amu) [mass excess = -80431.769 ± 3.124 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
318.646 ± 0.832 (keV)
Strong Gamma-rays from Decay of Ce-144 (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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40.98 0.26 B-
80.12 1.36 B-
133.51 11.09 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- 284.91 D 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ce-144.
Figures of cross sections, Ce-144: 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-143 (Z= 58, A=143), MT=102 (n,γ)
Ce-144 (Z= 58, A=144), MT= 2 (Elastic scattering)
Ce-144 (Z= 58, A=144), MT= 4 (Inelastic scattering)
Nd-146 (Z= 60, A=146), MT=106 (n,3He)
Nd-147 (Z= 60, A=147), MT=107 (n,α)
Nd-148 (Z= 60, A=148), MT= 22 (n,nα)
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-144 U-235 Thermal 3.449310e-04 2.207560e-04
Ce-144 U-235 Fast 1.676440e-04 1.072920e-04
Ce-144 U-235 High 2.165780e-03 1.386110e-03
Ce-144 U-238 Fast 1.431530e-05 9.161820e-06
Ce-144 U-238 High 1.566810e-04 1.002760e-04
Ce-144 Pu-239 Thermal 1.163910e-03 7.449000e-04
Ce-144 Pu-239 Fast 1.642990e-03 1.051520e-03
Ce-144 Pu-239 High 5.061160e-03 3.239140e-03
Ce-144 Pu-241 Thermal 1.282310e-04 8.206760e-05
Ce-144 Pu-241 Fast 2.100620e-04 1.344400e-04
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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-144 U-235 Thermal 5.491390e-02 3.935420e-04
Ce-144 U-235 Fast 5.278540e-02 7.442290e-04
Ce-144 U-235 High 3.173400e-02 8.884940e-04
Ce-144 U-238 Fast 4.554260e-02 6.398150e-04
Ce-144 U-238 High 3.728310e-02 1.043840e-03
Ce-144 Pu-239 Thermal 3.738850e-02 2.618070e-04
Ce-144 Pu-239 Fast 3.671800e-02 3.672670e-04
Ce-144 Pu-239 High 2.682010e-02 1.072250e-03
Ce-144 Pu-241 Thermal 4.228540e-02 4.228990e-04
Ce-144 Pu-241 Fast 4.168350e-02 2.502800e-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