55-Cs-133
Spin
Level energy(keV) Spin & Parity
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ground state 7/2+
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)
132.905451961 ± 0.000000008 (amu) [mass excess = -88070.931 ± 0.008 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-517.343 ± 0.993 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Cs-133.
Figures of cross sections, Cs-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
Cs-133 (Z= 55, A=133), MT= 2 (Elastic scattering)
Cs-133 (Z= 55, A=133), MT= 4 (Inelastic scattering)
Cs-134 (Z= 55, A=134), MT= 16 (n,2n)
Cs-135 (Z= 55, A=135), MT= 17 (n,3n)
Ba-134 (Z= 56, A=134), MT= 28 (n,np)
Ba-134 (Z= 56, A=134), MT=104 (n,d)
Ba-135 (Z= 56, A=135), MT= 32 (n,nd)
Ba-135 (Z= 56, A=135), MT=105 (n,t)
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-133 U-235 Thermal 7.907410e-09 2.530370e-09
Cs-133 U-235 Fast 7.504500e-10 4.802890e-10
Cs-133 U-235 High 8.341440e-06 5.338520e-06
Cs-133 U-238 Fast 5.321980e-11 3.406070e-11
Cs-133 U-238 High 7.388040e-08 4.728350e-08
Cs-133 Pu-239 Thermal 2.039670e-07 1.305390e-07
Cs-133 Pu-239 Fast 2.169650e-07 1.388580e-07
Cs-133 Pu-239 High 5.742720e-05 3.675340e-05
Cs-133 Pu-241 Thermal 1.450240e-09 9.281490e-10
Cs-133 Pu-241 Fast 4.006990e-09 2.564470e-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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Cs-133 U-235 Thermal 6.689360e-02 2.538660e-04
Cs-133 U-235 Fast 6.710080e-02 3.624180e-04
Cs-133 U-235 High 5.537410e-02 3.318470e-03
Cs-133 U-238 Fast 6.760790e-02 3.380610e-04
Cs-133 U-238 High 6.024080e-02 8.451910e-04
Cs-133 Pu-239 Thermal 7.015580e-02 3.508860e-04
Cs-133 Pu-239 Fast 6.970170e-02 3.486290e-04
Cs-133 Pu-239 High 4.868970e-02 3.892720e-03
Cs-133 Pu-241 Thermal 6.730560e-02 4.713500e-04
Cs-133 Pu-241 Fast 6.454980e-02 9.053410e-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