55-Cs-136
Spin
Level energy(keV) Spin & Parity
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ground state 5+
ground state(+X) 8-
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)
135.907311358 ± 0.000002015 (amu) [mass excess = -86338.914 ± 1.877 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2548.224 ± 1.857 (keV)
Strong Gamma-rays from Decay of Cs-136 (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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340.55 42.17 B-
818.51 99.7 B-
1048.07 79.76 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- 13.16 D 3
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cs-136.
Figures of cross sections, Cs-136: 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
Cs-135 (Z= 55, A=135), MT=102 (n,γ)
Cs-136 (Z= 55, A=136), MT= 2 (Elastic scattering)
Cs-136 (Z= 55, A=136), MT= 4 (Inelastic scattering)
Cs-137 (Z= 55, A=137), MT= 16 (n,2n)
Ba-136 (Z= 56, A=136), MT=103 (n,p)
Ba-137 (Z= 56, A=137), MT= 28 (n,np)
Ba-137 (Z= 56, A=137), MT=104 (n,d)
Ba-138 (Z= 56, A=138), MT=105 (n,t)
La-138 (Z= 57, A=138), MT=106 (n,3He)
La-139 (Z= 57, A=139), MT=107 (n,α)
La-140 (Z= 57, A=140), 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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Cs-136 U-235 Thermal 3.483390e-05 2.229370e-05
Cs-136 U-235 Fast 6.823340e-05 4.366940e-05
Cs-136 U-235 High 9.708780e-04 6.213600e-04
Cs-136 U-238 Fast 5.598890e-06 3.583290e-06
Cs-136 U-238 High 9.122710e-05 5.838560e-05
Cs-136 Pu-239 Thermal 6.137500e-04 3.928000e-04
Cs-136 Pu-239 Fast 7.175220e-04 4.592140e-04
Cs-136 Pu-239 High 3.233430e-03 2.069390e-03
Cs-136 Pu-241 Thermal 8.892620e-05 5.691280e-05
Cs-136 Pu-241 Fast 8.841540e-05 5.658590e-05
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Cs-136m U-235 Thermal 2.045800e-05 1.309310e-05
Cs-136m U-235 Fast 4.880500e-05 3.123520e-05
Cs-136m U-235 High 1.292240e-03 8.270310e-04
Cs-136m U-238 Fast 4.004690e-06 2.563000e-06
Cs-136m U-238 High 1.214240e-04 7.771140e-05
Cs-136m Pu-239 Thermal 3.604560e-04 2.306920e-04
Cs-136m Pu-239 Fast 5.132190e-04 3.284600e-04
Cs-136m Pu-239 High 4.303700e-03 2.754360e-03
Cs-136m Pu-241 Thermal 5.222650e-05 3.342500e-05
Cs-136m Pu-241 Fast 6.324050e-05 4.047390e-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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Cs-136 U-235 Thermal 5.529190e-05 3.538680e-05
Cs-136 U-235 Fast 1.170380e-04 7.490460e-05
Cs-136 U-235 High 2.263120e-03 1.353510e-03
Cs-136 U-238 Fast 9.603580e-06 6.146290e-06
Cs-136 U-238 High 2.126510e-04 1.272210e-04
Cs-136 Pu-239 Thermal 9.742070e-04 6.234930e-04
Cs-136 Pu-239 Fast 1.230740e-03 7.876730e-04
Cs-136 Pu-239 High 7.537130e-03 4.510770e-03
Cs-136 Pu-241 Thermal 1.411530e-04 9.033760e-05
Cs-136 Pu-241 Fast 1.516560e-04 9.705980e-05
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Cs-136m U-235 Thermal 2.045800e-05 1.309310e-05
Cs-136m U-235 Fast 4.880500e-05 3.123520e-05
Cs-136m U-235 High 1.292240e-03 8.258060e-04
Cs-136m U-238 Fast 4.004690e-06 2.562070e-06
Cs-136m U-238 High 1.214240e-04 7.762720e-05
Cs-136m Pu-239 Thermal 3.604560e-04 2.306920e-04
Cs-136m Pu-239 Fast 5.132190e-04 3.284600e-04
Cs-136m Pu-239 High 4.303700e-03 2.752580e-03
Cs-136m Pu-241 Thermal 5.222650e-05 3.341960e-05
Cs-136m Pu-241 Fast 6.324050e-05 4.047390e-05
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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