41-Nb-95
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
2.35690E+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)
94.906832404 ± 0.000000709 (amu) [mass excess = -86785.057 ± 0.660 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
925.567 ± 0.495 (keV)
Strong Gamma-rays from Decay of Nb- 95 (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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235.69 24.83 IT
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204.12 0.03 B-
561.88 0.01 B-
765.80 99.81 B-
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204.12 2.3 B-
582.08 0.05 B-
786.19 0.01 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- 34.991 D 6
B- 3.61 D 3
IT 3.61 D 3
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nb-95.
Figures of cross sections, Nb-95: 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- 94 (Z= 41, A= 94), MT=102 (n,γ)
Nb- 95 (Z= 41, A= 95), MT= 2 (Elastic scattering)
Nb- 95 (Z= 41, A= 95), MT= 4 (Inelastic scattering)
Mo- 95 (Z= 42, A= 95), MT=103 (n,p)
Mo- 96 (Z= 42, A= 96), MT= 28 (n,np)
Mo- 96 (Z= 42, A= 96), MT=104 (n,d)
Mo- 97 (Z= 42, A= 97), MT= 32 (n,nd)
Mo- 97 (Z= 42, A= 97), MT=105 (n,t)
Tc- 99 (Z= 43, A= 99), 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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Nb- 95 U-235 Thermal 1.060410e-06 6.786600e-07
Nb- 95 U-235 Fast 4.421270e-08 2.829620e-08
Nb- 95 U-235 High 1.183550e-05 7.574720e-06
Nb- 95 U-238 Fast 2.305500e-09 1.475520e-09
Nb- 95 U-238 High 1.767270e-07 1.131050e-07
Nb- 95 Pu-239 Thermal 5.658750e-06 3.621600e-06
Nb- 95 Pu-239 Fast 1.924940e-06 1.231960e-06
Nb- 95 Pu-239 High 4.485530e-05 2.870740e-05
Nb- 95 Pu-241 Thermal 8.965920e-08 5.738200e-08
Nb- 95 Pu-241 Fast 5.861190e-08 3.751160e-08
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Nb- 95m U-235 Thermal 2.455140e-07 1.571290e-07
Nb- 95m U-235 Fast 8.927570e-09 5.713640e-09
Nb- 95m U-235 High 1.492770e-06 9.553760e-07
Nb- 95m U-238 Fast 4.655330e-10 2.979410e-10
Nb- 95m U-238 High 2.228990e-08 1.426560e-08
Nb- 95m Pu-239 Thermal 1.310150e-06 8.385010e-07
Nb- 95m Pu-239 Fast 3.886900e-07 2.487620e-07
Nb- 95m Pu-239 High 5.657430e-06 3.620750e-06
Nb- 95m Pu-241 Thermal 2.075850e-08 1.328550e-08
Nb- 95m Pu-241 Fast 1.183510e-08 7.574460e-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)
-----------------------------------------------------------
Nb- 95 U-235 Thermal 6.493260e-02 9.154580e-04
Nb- 95 U-235 Fast 6.415550e-02 4.792850e-04
Nb- 95 U-235 High 5.180020e-02 1.449880e-03
Nb- 95 U-238 Fast 5.140410e-02 5.140500e-04
Nb- 95 U-238 High 4.894860e-02 9.788350e-04
Nb- 95 Pu-239 Thermal 4.816180e-02 6.749650e-04
Nb- 95 Pu-239 Fast 4.668420e-02 6.546460e-04
Nb- 95 Pu-239 High 3.929340e-02 2.357230e-03
Nb- 95 Pu-241 Thermal 3.924470e-02 7.852020e-04
Nb- 95 Pu-241 Fast 3.787320e-02 1.517500e-03
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Nb- 95m U-235 Thermal 5.849220e-04 6.622900e-05
Nb- 95m U-235 Fast 5.776990e-04 6.582010e-05
Nb- 95m U-235 High 4.678110e-04 5.306830e-05
Nb- 95m U-238 Fast 4.628700e-04 5.168620e-05
Nb- 95m U-238 High 4.407800e-04 4.940060e-05
Nb- 95m Pu-239 Thermal 4.349230e-04 4.913060e-05
Nb- 95m Pu-239 Fast 4.207380e-04 4.721500e-05
Nb- 95m Pu-239 High 3.590240e-04 4.573060e-05
Nb- 95m Pu-241 Thermal 3.534000e-04 4.069280e-05
Nb- 95m Pu-241 Fast 3.410420e-04 5.653980e-05
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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