54-Xe-130
Spin
Level energy(keV) Spin & Parity
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ground state 0+
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)
129.903509349 ± 0.000000010 (amu) [mass excess = -89880.462 ± 0.009 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2980.719 ± 8.357 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Xe-130.
Figures of cross sections, Xe-130: 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-129 (Z= 54, A=129), MT=102 (n,γ)
Xe-130 (Z= 54, A=130), MT= 2 (Elastic scattering)
Xe-130 (Z= 54, A=130), MT= 4 (Inelastic scattering)
Xe-131 (Z= 54, A=131), MT= 16 (n,2n)
Xe-132 (Z= 54, A=132), MT= 17 (n,3n)
Cs-133 (Z= 55, A=133), MT= 33 (n,nt)
Ba-132 (Z= 56, A=132), MT=106 (n,3He)
Ba-134 (Z= 56, A=134), 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-130 U-235 Thermal 1.966870e-10 6.293970e-11
Xe-130 U-235 Fast 1.896080e-11 1.213500e-11
Xe-130 U-235 High 1.031410e-06 6.601040e-07
Xe-130 U-238 High 5.886410e-09 3.767310e-09
Xe-130 Pu-239 Thermal 2.939530e-08 1.881310e-08
Xe-130 Pu-239 Fast 1.969690e-08 1.260600e-08
Xe-130 Pu-239 High 1.581030e-05 1.011860e-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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Xe-130 U-235 Thermal 2.212670e-06 3.552470e-07
Xe-130 U-235 Fast 1.776520e-07 1.136980e-07
Xe-130 U-235 High 2.610180e-04 1.668100e-04
Xe-130 U-238 Fast 4.231580e-14 8.450340e-17
Xe-130 U-238 High 9.566300e-06 6.112050e-06
Xe-130 Pu-239 Thermal 4.693200e-05 6.571940e-07
Xe-130 Pu-239 Fast 3.016480e-05 1.930550e-05
Xe-130 Pu-239 High 1.344240e-03 8.597440e-04
Xe-130 Pu-241 Thermal 8.411360e-12 1.373030e-15
Xe-130 Pu-241 Fast 4.626520e-12 1.347920e-14
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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