34-Se-79
Spin
Level energy(keV) Spin & Parity
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ground state 7/2+
9.57700E+01 1/2-
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)
78.918499287 ± 0.000000241 (amu) [mass excess = -75917.425 ± 0.225 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
150.630 ± 1.302 (keV)
Strong Gamma-rays from Decay of Se- 79 (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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95.73 9.62 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
B- 2.95E+5 Y 38
IT 3.92 M 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Se-79.
Figures of cross sections, Se-79: 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
Se- 78 (Z= 34, A= 78), MT=102 (n,γ)
Se- 79 (Z= 34, A= 79), MT= 2 (Elastic scattering)
Se- 79 (Z= 34, A= 79), MT= 4 (Inelastic scattering)
Se- 80 (Z= 34, A= 80), MT= 16 (n,2n)
Br- 79 (Z= 35, A= 79), MT=103 (n,p)
Br- 81 (Z= 35, A= 81), MT= 32 (n,nd)
Br- 81 (Z= 35, A= 81), MT=105 (n,t)
Kr- 82 (Z= 36, A= 82), MT=107 (n,α)
Kr- 83 (Z= 36, A= 83), 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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Se- 79 U-235 Thermal 1.095010e-07 7.008070e-08
Se- 79 U-235 Fast 1.380130e-07 8.832810e-08
Se- 79 U-235 High 3.329210e-06 2.130700e-06
Se- 79 U-238 Fast 6.908630e-09 4.421530e-09
Se- 79 U-238 High 5.336130e-07 3.415120e-07
Se- 79 Pu-239 Thermal 1.982520e-06 1.268810e-06
Se- 79 Pu-239 Fast 1.462120e-06 9.357570e-07
Se- 79 Pu-239 High 5.382730e-06 3.444950e-06
Se- 79 Pu-241 Thermal 1.743820e-07 1.116040e-07
Se- 79 Pu-241 Fast 1.282350e-07 8.207010e-08
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Se- 79m U-235 Thermal 1.679770e-08 1.075060e-08
Se- 79m U-235 Fast 1.846430e-08 1.181720e-08
Se- 79m U-235 High 2.777350e-07 1.777510e-07
Se- 79m U-238 Fast 9.242840e-10 5.915420e-10
Se- 79m U-238 High 4.451600e-08 2.849020e-08
Se- 79m Pu-239 Thermal 3.041240e-07 1.946400e-07
Se- 79m Pu-239 Fast 1.956120e-07 1.251920e-07
Se- 79m Pu-239 High 4.490470e-07 2.873900e-07
Se- 79m Pu-241 Thermal 2.675060e-08 1.712040e-08
Se- 79m Pu-241 Fast 1.715610e-08 1.097990e-08
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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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Se- 79 U-235 Thermal 4.467130e-04 3.578770e-05
Se- 79 U-235 Fast 9.069400e-04 2.089750e-04
Se- 79 U-235 High 1.682380e-03 3.862520e-04
Se- 79 U-238 Fast 3.272080e-04 1.045550e-04
Se- 79 U-238 High 1.335150e-03 4.265120e-04
Se- 79 Pu-239 Thermal 4.364530e-04 1.746000e-05
Se- 79 Pu-239 Fast 6.076530e-04 9.723230e-05
Se- 79 Pu-239 High 8.636460e-04 1.984430e-04
Se- 79 Pu-241 Thermal 1.496190e-04 3.440560e-05
Se- 79 Pu-241 Fast 3.584450e-04 8.248750e-05
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Se- 79m U-235 Thermal 4.372250e-04 3.713310e-05
Se- 79m U-235 Fast 8.877600e-04 2.914280e-04
Se- 79m U-235 High 1.643790e-03 5.372920e-04
Se- 79m U-238 Fast 3.203300e-04 1.471680e-04
Se- 79m U-238 High 1.306590e-03 6.000860e-04
Se- 79m Pu-239 Thermal 4.253530e-04 3.595070e-05
Se- 79m Pu-239 Fast 5.934650e-04 1.944200e-04
Se- 79m Pu-239 High 8.402490e-04 2.749230e-04
Se- 79m Pu-241 Thermal 1.463060e-04 4.791590e-05
Se- 79m Pu-241 Fast 3.507930e-04 1.149820e-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