54-Xe-131
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
1.63930E+02 11/2-
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)
130.905084057 ± 0.000000236 (amu) [mass excess = -88413.631 ± 0.220 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-354.752 ± 4.976 (keV)
Strong Gamma-rays from Decay of Xe-131 (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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163.93 1.95 IT
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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
IT 11.86 D 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Xe-131.
Figures of cross sections, Xe-131: 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
Xe-130 (Z= 54, A=130), MT=102 (n,γ)
Xe-131 (Z= 54, A=131), MT= 2 (Elastic scattering)
Xe-131 (Z= 54, A=131), MT= 4 (Inelastic scattering)
Xe-132 (Z= 54, A=132), MT= 16 (n,2n)
Xe-133 (Z= 54, A=133), MT= 17 (n,3n)
Cs-133 (Z= 55, A=133), MT= 32 (n,nd)
Cs-133 (Z= 55, A=133), MT= 41 (n,2np)
Cs-133 (Z= 55, A=133), MT=105 (n,t)
Cs-134 (Z= 55, A=134), MT= 33 (n,nt)
Ba-134 (Z= 56, A=134), MT=107 (n,α)
Ba-135 (Z= 56, A=135), 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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Xe-131 U-235 Thermal 1.433420e-09 9.173870e-10
Xe-131 U-235 Fast 8.545640e-10 5.469210e-10
Xe-131 U-235 High 1.986040e-06 1.271070e-06
Xe-131 U-238 Fast 1.123430e-11 3.594960e-12
Xe-131 U-238 High 2.381500e-09 7.620780e-10
Xe-131 Pu-239 Thermal 1.239190e-07 7.930860e-08
Xe-131 Pu-239 Fast 9.482240e-08 6.068620e-08
Xe-131 Pu-239 High 1.940190e-05 1.241720e-05
Xe-131 Pu-241 Thermal 2.344380e-09 1.500400e-09
Xe-131 Pu-241 Fast 2.515020e-09 1.609610e-09
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Xe-131m U-235 Thermal 3.458790e-09 2.213630e-09
Xe-131m U-235 Fast 2.394730e-09 1.532630e-09
Xe-131m U-235 High 9.109160e-06 5.829860e-06
Xe-131m U-238 Fast 3.148170e-11 2.014820e-11
Xe-131m U-238 High 1.092290e-08 6.990710e-09
Xe-131m Pu-239 Thermal 2.990130e-07 1.913690e-07
Xe-131m Pu-239 Fast 2.657190e-07 1.700600e-07
Xe-131m Pu-239 High 8.898840e-05 5.695260e-05
Xe-131m Pu-241 Thermal 5.656920e-09 3.620430e-09
Xe-131m Pu-241 Fast 7.047790e-09 4.510590e-09
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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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Xe-131 U-235 Thermal 2.890920e-02 1.445530e-04
Xe-131 U-235 Fast 3.217610e-02 2.261750e-04
Xe-131 U-235 High 4.108590e-02 1.150280e-03
Xe-131 U-238 Fast 3.292630e-02 3.295810e-04
Xe-131 U-238 High 3.995190e-02 5.596120e-04
Xe-131 Pu-239 Thermal 3.856360e-02 1.928200e-04
Xe-131 Pu-239 Fast 3.878300e-02 1.939190e-04
Xe-131 Pu-239 High 4.368600e-02 1.222740e-03
Xe-131 Pu-241 Thermal 3.101650e-02 4.341950e-04
Xe-131 Pu-241 Fast 3.362660e-02 6.724900e-04
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Xe-131m U-235 Thermal 3.180050e-04 8.688120e-05
Xe-131m U-235 Fast 3.539390e-04 9.721540e-05
Xe-131m U-235 High 4.609320e-04 1.245730e-04
Xe-131m U-238 Fast 3.621900e-04 9.873430e-05
Xe-131m U-238 High 4.394820e-04 1.204910e-04
Xe-131m Pu-239 Thermal 4.244940e-04 1.162020e-04
Xe-131m Pu-239 Fast 4.268750e-04 1.168600e-04
Xe-131m Pu-239 High 5.683380e-04 1.716540e-04
Xe-131m Pu-241 Thermal 3.411870e-04 9.454110e-05
Xe-131m Pu-241 Fast 3.698990e-04 1.258730e-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