57-La-140
Spin
Level energy(keV) Spin & Parity
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ground state 3-
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)
139.909480635 ± 0.000002438 (amu) [mass excess = -84318.245 ± 2.272 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
3760.933 ± 1.797 (keV)
Strong Gamma-rays from Decay of La-140 (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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487.02 45.51 B-
815.77 23.28 B-
1596.21 95.4 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- 1.67855 D 12
Cross Sections (taken from JENDL-4.0)
Table of cross sections, La-140.
Figures of cross sections, La-140: 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
La-139 (Z= 57, A=139), MT=102 (n,γ)
La-140 (Z= 57, A=140), MT= 2 (Elastic scattering)
La-140 (Z= 57, A=140), MT= 4 (Inelastic scattering)
Ce-140 (Z= 58, A=140), MT=103 (n,p)
Ce-141 (Z= 58, A=141), MT= 28 (n,np)
Ce-141 (Z= 58, A=141), MT=104 (n,d)
Ce-142 (Z= 58, A=142), MT= 32 (n,nd)
Ce-142 (Z= 58, A=142), MT=105 (n,t)
Pr-143 (Z= 59, A=143), MT=107 (n,α)
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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La-140 U-235 Thermal 5.207710e-05 3.332930e-05
La-140 U-235 Fast 2.035790e-06 1.302910e-06
La-140 U-235 High 3.344680e-04 2.140600e-04
La-140 U-238 Fast 2.480930e-07 1.587790e-07
La-140 U-238 High 4.125490e-05 2.640310e-05
La-140 Pu-239 Thermal 1.019540e-04 6.525050e-05
La-140 Pu-239 Fast 9.868410e-05 6.315780e-05
La-140 Pu-239 High 1.408110e-03 9.011920e-04
La-140 Pu-241 Thermal 4.190680e-06 2.682030e-06
La-140 Pu-241 Fast 3.887080e-06 2.487730e-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)
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La-140 U-235 Thermal 6.208720e-02 6.315620e-04
La-140 U-235 Fast 5.965020e-02 6.115780e-04
La-140 U-235 High 4.534690e-02 1.269530e-03
La-140 U-238 Fast 5.815660e-02 4.070880e-04
La-140 U-238 High 4.615310e-02 6.468990e-04
La-140 Pu-239 Thermal 5.363460e-02 7.511640e-04
La-140 Pu-239 Fast 5.331920e-02 5.334400e-04
La-140 Pu-239 High 3.844020e-02 2.305140e-03
La-140 Pu-241 Thermal 5.766940e-02 1.153340e-03
La-140 Pu-241 Fast 5.301400e-02 2.122930e-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