43-Tc-99
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
1.42683E+02 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)
98.906250844 ± 0.000001037 (amu) [mass excess = -87326.776 ± 0.966 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
295.062 ± 1.133 (keV)
Strong Gamma-rays from Decay of Tc- 99 (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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89.5 7.E-04 B-
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2.17 -- IT
140.51 89. IT
142.63 0.02 IT
89.6 -- B-
232.8 9.E-06 B-
322.4 1.E-04 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- 6.0067 H 5
B- 2.111E+5 Y 12
IT 6.0067 H 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Tc-99.
Figures of cross sections, Tc-99: 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
Tc- 99 (Z= 43, A= 99), MT= 2 (Elastic scattering)
Tc- 99 (Z= 43, A= 99), MT= 4 (Inelastic scattering)
Ru- 99 (Z= 44, A= 99), MT=103 (n,p)
Ru-100 (Z= 44, A=100), MT= 28 (n,np)
Ru-100 (Z= 44, A=100), MT=104 (n,d)
Ru-101 (Z= 44, A=101), MT= 32 (n,nd)
Ru-101 (Z= 44, A=101), MT=105 (n,t)
Rh-103 (Z= 45, A=103), 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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Tc- 99 U-235 Thermal 1.231460e-09 7.881390e-10
Tc- 99 U-235 Fast 4.852190e-10 3.105400e-10
Tc- 99 U-235 High 8.145250e-07 5.212960e-07
Tc- 99 U-238 Fast 1.995050e-11 1.276830e-11
Tc- 99 U-238 High 5.114230e-09 3.273110e-09
Tc- 99 Pu-239 Thermal 1.202390e-07 7.695250e-08
Tc- 99 Pu-239 Fast 7.278820e-08 4.658450e-08
Tc- 99 Pu-239 High 6.410190e-06 4.102520e-06
Tc- 99 Pu-241 Thermal 1.613710e-09 1.032770e-09
Tc- 99 Pu-241 Fast 1.030900e-09 6.597790e-10
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Tc- 99m U-235 Thermal 2.851170e-10 1.824750e-10
Tc- 99m U-235 Fast 9.797700e-11 6.270520e-11
Tc- 99m U-235 High 1.027330e-07 6.574880e-08
Tc- 99m U-238 Fast 4.028460e-12 2.578210e-12
Tc- 99m U-238 High 6.450380e-10 4.128250e-10
Tc- 99m Pu-239 Thermal 2.783850e-08 1.781660e-08
Tc- 99m Pu-239 Fast 1.469760e-08 9.406490e-09
Tc- 99m Pu-239 High 8.084920e-07 5.174350e-07
Tc- 99m Pu-241 Thermal 3.736170e-10 2.391150e-10
Tc- 99m Pu-241 Fast 2.081630e-10 1.332250e-10
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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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Tc- 99 U-235 Thermal 6.138470e-02 6.794330e-04
Tc- 99 U-235 Fast 5.977410e-02 6.861130e-04
Tc- 99 U-235 High 5.163510e-02 1.464660e-03
Tc- 99 U-238 Fast 6.258370e-02 1.248160e-03
Tc- 99 U-238 High 5.766420e-02 8.353120e-04
Tc- 99 Pu-239 Thermal 6.232680e-02 8.945320e-04
Tc- 99 Pu-239 Fast 6.002800e-02 1.213570e-03
Tc- 99 Pu-239 High 4.766000e-02 1.906830e-03
Tc- 99 Pu-241 Thermal 6.002950e-02 1.261260e-03
Tc- 99 Pu-241 Fast 5.569900e-02 3.342530e-03
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Tc- 99m U-235 Thermal 5.340660e-02 8.301400e-04
Tc- 99m U-235 Fast 5.200530e-02 7.891200e-04
Tc- 99m U-235 High 4.492340e-02 1.293900e-03
Tc- 99m U-238 Fast 5.444970e-02 7.785210e-04
Tc- 99m U-238 High 5.016960e-02 7.039320e-04
Tc- 99m Pu-239 Thermal 5.422610e-02 8.812300e-04
Tc- 99m Pu-239 Fast 5.222620e-02 1.133580e-03
Tc- 99m Pu-239 High 4.146010e-02 1.704340e-03
Tc- 99m Pu-241 Thermal 5.222750e-02 1.075620e-03
Tc- 99m Pu-241 Fast 4.845980e-02 2.925840e-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