41-Nb-94
Spin
Level energy(keV) Spin & Parity
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ground state 6+
4.08920E+01 3+
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)
93.907278836 ± 0.000001958 (amu) [mass excess = -86369.207 ± 1.824 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2043.636 ± 1.809 (keV)
Strong Gamma-rays from Decay of Nb- 94 (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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40.94 0.07 IT
702. 3.E-03 B-
871. 0.5 B-
993. 7.E-04 B-
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702.65 -- B-
871.09 -- 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- 6.263 M 4
B- 2.03E+4 Y 16
IT 6.263 M 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nb-94.
Figures of cross sections, Nb-94: 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
Nb- 93 (Z= 41, A= 93), MT=102 (n,γ)
Nb- 94 (Z= 41, A= 94), MT= 2 (Elastic scattering)
Nb- 94 (Z= 41, A= 94), MT= 4 (Inelastic scattering)
Nb- 95 (Z= 41, A= 95), MT= 16 (n,2n)
Mo- 94 (Z= 42, A= 94), MT=103 (n,p)
Mo- 95 (Z= 42, A= 95), MT= 28 (n,np)
Mo- 95 (Z= 42, A= 95), MT=104 (n,d)
Mo- 96 (Z= 42, A= 96), MT= 32 (n,nd)
Mo- 96 (Z= 42, A= 96), 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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Nb- 94 U-235 Thermal 1.447590e-09 9.264540e-10
Nb- 94 U-235 Fast 5.759830e-10 3.686290e-10
Nb- 94 U-235 High 7.397910e-07 4.734660e-07
Nb- 94 U-238 Fast 2.323330e-11 1.486930e-11
Nb- 94 U-238 High 5.363270e-09 3.432490e-09
Nb- 94 Pu-239 Thermal 9.519640e-08 6.092570e-08
Nb- 94 Pu-239 Fast 6.302800e-08 4.033790e-08
Nb- 94 Pu-239 High 3.974340e-06 2.543580e-06
Nb- 94 Pu-241 Thermal 1.714320e-09 1.097160e-09
Nb- 94 Pu-241 Fast 9.752010e-10 6.241280e-10
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Nb- 94m U-235 Thermal 1.018490e-09 6.518320e-10
Nb- 94m U-235 Fast 3.441180e-10 2.202350e-10
Nb- 94m U-235 High 2.585770e-07 1.654890e-07
Nb- 94m U-238 Fast 1.388060e-11 8.883580e-12
Nb- 94m U-238 High 1.874610e-09 1.199750e-09
Nb- 94m Pu-239 Thermal 6.697800e-08 4.286600e-08
Nb- 94m Pu-239 Fast 3.765570e-08 2.409970e-08
Nb- 94m Pu-239 High 1.389140e-06 8.890500e-07
Nb- 94m Pu-241 Thermal 1.206160e-09 7.719390e-10
Nb- 94m Pu-241 Fast 5.826280e-10 3.728820e-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)
-----------------------------------------------------------
Nb- 94 U-235 Thermal 2.460990e-09 1.574220e-09
Nb- 94 U-235 Fast 9.183800e-10 5.869860e-10
Nb- 94 U-235 High 9.970760e-07 6.381290e-07
Nb- 94 U-238 Fast 3.704450e-11 2.363220e-11
Nb- 94 U-238 High 7.228510e-09 4.626250e-09
Nb- 94 Pu-239 Thermal 1.618400e-07 1.033670e-07
Nb- 94 Pu-239 Fast 1.004950e-07 6.431720e-08
Nb- 94 Pu-239 High 5.356530e-06 3.428180e-06
Nb- 94 Pu-241 Thermal 2.914440e-09 1.864990e-09
Nb- 94 Pu-241 Fast 1.554920e-09 9.945180e-10
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Nb- 94m U-235 Thermal 1.018490e-09 6.518320e-10
Nb- 94m U-235 Fast 3.441180e-10 2.202350e-10
Nb- 94m U-235 High 2.585770e-07 1.652440e-07
Nb- 94m U-238 Fast 1.388060e-11 8.880330e-12
Nb- 94m U-238 High 1.874610e-09 1.198460e-09
Nb- 94m Pu-239 Thermal 6.697800e-08 4.286600e-08
Nb- 94m Pu-239 Fast 3.765570e-08 2.409970e-08
Nb- 94m Pu-239 High 1.389140e-06 8.884740e-07
Nb- 94m Pu-241 Thermal 1.206160e-09 7.718130e-10
Nb- 94m Pu-241 Fast 5.826280e-10 3.728820e-10
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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