54-Xe-133
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
2.33221E+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)
132.905910751 ± 0.000002576 (amu) [mass excess = -87643.571 ± 2.400 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
427.360 ± 2.400 (keV)
Strong Gamma-rays from Decay of Xe-133 (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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233.22 10. IT
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79.62 0.27 B-
81.00 38. B-
160.61 0.07 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- 5.243 D 1
IT 2.19 D 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Xe-133.
Figures of cross sections, Xe-133: 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-132 (Z= 54, A=132), MT=102 (n,γ)
Xe-133 (Z= 54, A=133), MT= 2 (Elastic scattering)
Xe-133 (Z= 54, A=133), MT= 4 (Inelastic scattering)
Xe-134 (Z= 54, A=134), MT= 16 (n,2n)
Xe-135 (Z= 54, A=135), MT= 17 (n,3n)
Cs-133 (Z= 55, A=133), MT=103 (n,p)
Cs-134 (Z= 55, A=134), MT= 28 (n,np)
Cs-134 (Z= 55, A=134), MT=104 (n,d)
Cs-135 (Z= 55, A=135), MT= 32 (n,nd)
Cs-135 (Z= 55, A=135), MT= 41 (n,2np)
Cs-135 (Z= 55, A=135), MT=105 (n,t)
Cs-136 (Z= 55, A=136), MT= 33 (n,nt)
Ba-135 (Z= 56, A=135), MT=106 (n,3He)
Ba-136 (Z= 56, A=136), MT=107 (n,α)
Ba-137 (Z= 56, A=137), 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-133 U-235 Thermal 7.465480e-06 4.479290e-07
Xe-133 U-235 Fast 1.492070e-05 8.952430e-07
Xe-133 U-235 High 3.081490e-04 1.972150e-04
Xe-133 U-238 Fast 4.312180e-06 2.759800e-06
Xe-133 U-238 High 3.104560e-05 9.934610e-06
Xe-133 Pu-239 Thermal 1.266940e-04 1.393640e-05
Xe-133 Pu-239 Fast 1.638490e-04 9.830940e-06
Xe-133 Pu-239 High 6.841090e-04 4.378300e-04
Xe-133 Pu-241 Thermal 2.534860e-06 1.622310e-06
Xe-133 Pu-241 Fast 5.303350e-06 3.394150e-06
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Xe-133m U-235 Thermal 1.801400e-05 1.152890e-05
Xe-133m U-235 Fast 4.181210e-05 2.675980e-05
Xe-133m U-235 High 1.413350e-03 9.045450e-04
Xe-133m U-238 Fast 1.208400e-05 7.733720e-06
Xe-133m U-238 High 1.423940e-04 9.113170e-05
Xe-133m Pu-239 Thermal 3.057080e-04 1.956530e-04
Xe-133m Pu-239 Fast 4.591500e-04 2.938560e-04
Xe-133m Pu-239 High 3.137730e-03 2.008150e-03
Xe-133m Pu-241 Thermal 6.116540e-06 3.914590e-06
Xe-133m Pu-241 Fast 1.486150e-05 9.511350e-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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Xe-133 U-235 Thermal 6.689360e-02 4.281190e-02
Xe-133 U-235 Fast 6.710080e-02 4.294460e-02
Xe-133 U-235 High 5.536570e-02 3.538450e-02
Xe-133 U-238 Fast 6.760790e-02 4.326900e-02
Xe-133 U-238 High 6.024070e-02 3.851150e-02
Xe-133 Pu-239 Thermal 7.015560e-02 4.489960e-02
Xe-133 Pu-239 Fast 6.970150e-02 4.460900e-02
Xe-133 Pu-239 High 4.863220e-02 3.098430e-02
Xe-133 Pu-241 Thermal 6.730560e-02 4.306420e-02
Xe-133 Pu-241 Fast 6.454980e-02 4.131190e-02
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Xe-133m U-235 Thermal 1.943810e-03 1.244050e-03
Xe-133m U-235 Fast 1.972680e-03 1.262510e-03
Xe-133m U-235 High 2.958310e-03 1.890480e-03
Xe-133m U-238 Fast 1.958720e-03 1.253580e-03
Xe-133m U-238 High 1.872330e-03 1.196940e-03
Xe-133m Pu-239 Thermal 2.313740e-03 1.480790e-03
Xe-133m Pu-239 Fast 2.448610e-03 1.567110e-03
Xe-133m Pu-239 High 4.428270e-03 2.832230e-03
Xe-133m Pu-241 Thermal 1.944270e-03 1.244000e-03
Xe-133m Pu-241 Fast 1.873310e-03 1.198920e-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